ML25100A147
| ML25100A147 | |
| Person / Time | |
|---|---|
| Site: | 99902078 |
| Issue date: | 04/10/2025 |
| From: | NRC |
| To: | NRC/NRR/DNRL/NRLB |
| References | |
| Download: ML25100A147 (4) | |
Text
From:
Thomas Hayden Sent:
Thursday, April 10, 2025 11:38 AM To:
NuScale-SDA-720DocsPEm Resource
Subject:
FW: Final Safety Evaluation for NuScale Extended Passive Cooling and Reactivity Control Methodology Prop and non-Prop Tommy Hayden Project Manager Email: thomas.hayden@nrc.gov Division of New and Renewed Licenses Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission From: Thomas Hayden Sent: Thursday, April 10, 2025 9:29 AM To: regulatoryaffairs@nuscalepower.com Cc: Griffith, Thomas <tgriffith@nuscalepower.com>; Bode, Amanda <abode@nuscalepower.com>;
Mahmoud -MJ-Jardaneh <Mahmoud.Jardaneh@nrc.gov>; Getachew Tesfaye
<Getachew.Tesfaye@nrc.gov>
Subject:
Final Safety Evaluation for NuScale Extended Passive Cooling and Reactivity Control Methodology Prop and non-Prop By letter dated March 28, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML25087A229 (Proprietary) and ML25087A228 (non-Proprietary)),
NuScale Power, LLC (NuScale), submitted Topical Report (TR) TR-124587, Revision 1, Extended Passive Cooling and Reactivity Control Methodology to the U.S. Nuclear Regulatory Commission (NRC). The NRC staff has prepared a final safety evaluation for TR-124587, Revision
- 1. The non-proprietary (ML25098A230) and proprietary (ML25098A229) final safety evaluations are enclosed. The NRC staff has found that TR-124587, Revision 1, is 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 as soon as possible following 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 a -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) 415-2956 or via e-mail address at Thomas.Hayden@nrc.gov. The attached documents are both password protected. Password to follow in a separate email.
Docket Nos. 99902078, 05200050 Sincerely, Tommy Hayden Project Manager Email: thomas.hayden@nrc.gov Division of New and Renewed Licenses Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
Hearing Identifier:
NuScale_SDA720_Doc_Public Email Number:
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Subject:
FW Final Safety Evaluation for NuScale Extended Passive Cooling and Reactivity Control Methodology Prop and non-Prop Sent Date:
4/10/2025 11:38:27 AM Received Date:
4/10/2025 11:38:29 AM From:
Thomas Hayden Created By:
Thomas.Hayden@nrc.gov Recipients:
"NuScale-SDA-720DocsPEm Resource" <NuScale-SDA-720DocsPEm.Resource@nrc.gov>
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