ML25324A208
| ML25324A208 | |
| Person / Time | |
|---|---|
| Site: | 07109367 |
| Issue date: | 11/25/2025 |
| From: | Michelle Gonzalez Storage and Transportation Licensing Branch |
| To: | Corcoran S Holtec |
| References | |
| EPID L-2025-LLA-0052 | |
| Download: ML25324A208 (0) | |
Text
Sean Corcoran, Licensing Engineer Holtec International 1 Holtec Blvd Camden, NJ 08104
SUBJECT:
REVISION 3 OF CERTIFICATE OF COMPLIANCE NO. 9367 FOR THE MODEL NO. HI-STAR 180D PACKAGE - REQUEST FOR ADDITIONAL INFORMATION
Dear Sean Corcoran:
By application dated March 14, 2025 (Agencywide Documents Access and Management System Accession No. ML25073A268), Holtec International applied for a renewal and an amendment to Certificate of Compliance No. 9367 for the Model No. HI-STAR 180D package.
In connection with our review, we need the information identified in the enclosure to this letter.
To assist us in scheduling the U.S. Nuclear Regulatory Commission staffs review of your response, we request that you provide this information within 10 calendar days from the date of this letter. Inform us at your earliest convenience, but no later than 5 calendar days from the date of this letter if you are not able to provide the information by that time frame. Additional information requested by this letter should be submitted in the form of revised pages. If you are unable to provide a response by the time frame provided in this letter and the quality of the response is not adequate, the proposed date for completing the review will be delayed.
Please reference Docket No. 71-9367 and Enterprise Project Identifier No. L-2025-LLA-0052 in future correspondence related to this request. The staff is available to meet and discuss your proposed responses. If you have any questions, I may be contacted at 301-415-3637.
Sincerely, Martin Ortiz Gonzalez, Project Manager Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9367 EPID L-2025-LLA-0052
Enclosure:
Request for Additional Information November 25, 2025 Signed by Gonzalez, Martin Ortiz on 11/25/25
ML25324A208 OFFICE NMSS/DFM NMSS/DFM NMSS/DFM NMSS/DFM NAME MOrtizGonzalez SFigueroa CStanko JPiotter DATE 11/20/2025 11/20/2025 11/20/2025 11/25/2025 OFFICE NMSS/DFM NMSS/DFM NAME YDiaz-Sanabria MOrtizGonzalez DATE 11/25/2025 11/25/2025
Enclosure Request for Additional Information Docket No. 71-9367 Certificate of Compliance No. 9367 Model No. HI-STAR 180D Transport Package Revision No. 03 By application dated March 14, 2025 (Agencywide Documents Access and Management System Accession No. ML25073A268), Holtec International applied for an amendment to Certificate of Compliance No. 9367 for the Model No. HI-STAR 180D package. This request for additional information identifies information needed by the U.S. Nuclear Regulatory Commission staff (the staff) in connection with its review of the application. The staff used guidance provided in NUREG--2216, Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material, in its review of the application.
The information below is needed by the staff to complete its review.
Chapter 3 - Thermal Evaluation RAI 3-1 Provide an updated thermal evaluation with revised component geometries (e.g.,
material thickness) to demonstrate that component temperatures would remain below acceptable material temperature limits during normal conditions of transport (NCT).
The staff evaluated the applicant's proposed changes (PCs) (ML25073A270) against the information found in the previous revision (ML20108F087) of the submitted safety analysis report (SAR). The following PCs are considered in the request for an updated thermal evaluation:
PC-1 through PC-5 (ML25073A270)
These PCs propose decreasing thickness of the inner lid shielding plate, the outer lid, the bottom lead gamma shield, and the bottom shield Holtite cavity lead, as well as reducing the radial gap of the outer lid to cask flange inner diameter.
Temperature values from the previous SAR (ML20108F087) indicate that some parts of the package were within 5 percent of their maximum allowable temperatures, even before the addition of the personnel barrier (required for compliance with maximum accessible surface temperature regulations). With the personnel barrier installed, the cladding, basket, shims, and containment shell all fell within 10 degrees Celsius of their respective maximum allowable NCT temperatures, and the temperature of the neutron shielding (Holtite) exceeded its NCT design temperature by
~2.5 percent.
This information is needed to demonstrate compliance with Title 10 of the Code of Federal Regulations (10 CFR) 71.71(c)(1).
2 General Information RAI-GEN-1 Revise the shielding, structural, and thermal justifications related to proposed change No. 22 included in the summary of changes submitted with Enclosure 1, Summary of proposed changes, to letter dated March 15, 2025 (ML25073A268). Proposed change No. 22 related to the containment boundary.
In letter dated March 15, 2025 (ML25073A268), Enclosure 1, Summary of proposed changes, the justifications for the proposed change No. 22 are transposed for the shielding, structural, and thermal disciplines. An excerpt from the summary of changes table is shown below.
The table needs to be revised to reflect accurate information about the changes requested.
This information is needed to demonstrate compliance with 10 CFR 71.33(a)(4).