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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
From:
Thomas Hayden To:
Regulatory Affairs Cc:
Griffith, Thomas; Cummings, Kristopher; Mahmoud -MJ-Jardaneh; Getachew Tesfaye
Subject:
896-A Version Verification for NuScale Topical Report TR-141299, Revision 1 Date:
Wednesday, June 4, 2025 9:49:00 AM Attachments:
image001.png NRC 896 - MBDBE Rev 1 signed.pdf Please find the attached completed NRC 896 form for the U.S. Nuclear Regulatory Commission staff -A version verification for Topical Report, TR-141299, Revision 1 NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events as defined by 10 CFR 50.155. If you have any questions, please feel free to contact me at Thomas.Hayden@nrc.gov.
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