ML22056A309
| ML22056A309 | |
| Person / Time | |
|---|---|
| Site: | 99902078 |
| Issue date: | 02/25/2022 |
| From: | Getachew Tesfaye NRC/NRR/DNRL/NRLB |
| To: | |
| Tesfaye G | |
| Shared Package | |
| ML22056A307 | List: |
| References | |
| TR-0920-71621, Rev 1 | |
| Download: ML22056A309 (1) | |
Text
1 Tesfaye, Getachew From:
Tesfaye, Getachew Sent:
Friday, February 25, 2022 10:53 AM To:
Regulatory Affairs Cc:
English, Liz; Shaver, Mark; Chitty, Mark; Murray, Demetrius; Bavol, Bruce; Dudek, Michael
Subject:
Final Safety Evaluation for NuScale Licensing Topical Report (TR)-0920-71621, Revision 1, "Building Design and Analysis Methodology for Safety-Related Structures Attachments:
Building Design TR Staff Final Safety Evaluation.pdf By letter dated December 18, 2020 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20353A404), NuScale Power, LLC (NuScale), submitted Licensing Topical Report (TR)-
0920-71621, Revision 0, Building Design and Analysis Methodology for Safety-Related Structures. By letter dated October 6, 2021 (ADAMS Accession No. ML21279A336), NuScale submitted Revision 1 of TR-0920-71621. The U.S. Nuclear Regulatory Commission (NRC) staff has prepared a final safety evaluation for Topical Report TR-0920-71621, Revision 1. The non-proprietary final safety evaluation is enclosed. The NRC staff has found that TR-0920-71621, Revision 1, acceptable for referencing in licensing applications for the NuScale small modular reactor design to the extent specified and under the conditions and limitations delineated in the enclosed final safety evaluation.
The NRC staff requests that NuScale publish the accepted version of this TR within three months of receipt of this electronic mail. The accepted version shall incorporate this electronic mail and the enclosed final safety evaluation after the title page. It must be well indexed such that information is readily located. Also, it must contain historical review information, including NRC requests for additional information and accepted responses. The accepted version of the TR shall include an -A (designated accepted) following the report identification number.
If the NRCs criteria or regulations change such that the NRC staffs conclusion in this electronic mail (that the TR is acceptable) is invalidated, NuScale and/or the applicant referencing the TR will be expected either to revise and resubmit its respective documentation or to submit justification for continued applicability of the TR without revision of the respective documentation.
If you have any questions or comments concerning this matter, I can be reached at (301) 415-8013 or via e-mail address at Getachew.Tesfaye@nrc.gov.
Sincerely, Getachew Tesfaye, Senior Project Manager New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No. 99902078