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MONTHYEARML23254A3602023-09-11011 September 2023
LLC, Submittal of Topical Report NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, TR-141299, Revision 0
Project stage: Request
ML23305A0042023-11-0303 November 2023
Completeness Determination for NuScale Topical Report TR-141299, NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, Revision 0
Project stage: Other
ML23304A4192023-11-0303 November 2023
Withholding Determination NRC Form 897 for Topical Report TR-141299, NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, Revision 0
Project stage: Other
ML23304A4182023-11-0303 November 2023
Email Transmitting NRC Form 897 for Withholding Determination Review of Topical Report TR-141299, NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, Revision 0
Project stage: Approval
ML24178A4012024-06-26026 June 2024
LLC, Response to NuScale Topical Report Audit Question
Project stage: Request
ML24178A3982024-06-26026 June 2024
LLC, Submittal of Topical Report NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, TR-141299-P, Revision 1 and Docketing of Resolved Audit Responses
Project stage: Request
ML24263A0042024-09-26026 September 2024
Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report TR 141299 P, Revision 1 NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis. NON-PROP
Project stage: Approval
ML25139A6082025-05-19019 May 2025
Email of 896-A Version Verification for NuScale Topical Report, TR-141299, Rev. 1
Project stage: Other
ML25139A6072025-05-19019 May 2025
Staff -A Verification Form 896 for NuScale Topical Report TR-141299-P-A, Revision 1 NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155
Project stage: Other
2024-06-26
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Text
1 Getachew Tesfaye From:
Getachew Tesfaye Sent:
Friday, November 03, 2023 8:31 PM To:
Regulatory Affairs Cc:
Griffith, Thomas; Fairbanks, Elisa; Mahmoud Jardaneh; Thomas Hayden
Subject:
Proprietary Determination for NuScale Power, LLC Topical Report TR-141299, "NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, Revision 0 Attachments:
LTR Withholding Determination NRC Form 897 Signed.pdf Attached please find the completed NRC Form 897 for the U.S. Nuclear Regulatory Commission staff proprietary determination review of NuScale Power, LLC Topical Report TR-141299, "NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, Revision 0. The LTR was submitted by letter dated September 11, 2023 (Agencywide Documents Access and Management System
[ADAMS] Accession Nos. ML23254A361 [proprietary] and ML23254A360 [nonproprietary]).
If you have any questions, please feel free to contact me at 301-415-8013.
Getachew Tesfaye, Senior Project Manager New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No.: 05200050