ML24215A045

LLC, Response to Sdaa Audit Question Number A-3.9.2-1

ML24215A045
Person / Time
Site:	05200050
Issue date:	08/02/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
Shared Package
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Download: ML24215A045 (1)

Text

Response to SDAA Audit Question Question Number: A-3.9.2-1 Receipt Date: 03/27/2023 Question:

NuScale standard design approval Final Safety Analysis Report (FSAR) Section 3.9.2.4, Flow-Induced Vibration Testing of Reactor Internals Before NuScale Power Module Operation references TR-121353, NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, Revision 0 and TR-121354, NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, Revision 0. However, the NRC staff needs additional information to make a safety finding. In the event a NuScale Power Module (NPM) operates at conditions where (( 2(a),(c),ECI Provide assessments of the dynamic loads on the IFRs and in particular on the long-term integrity of the IFR bolting system and expanding collets between the IFRs and the inner tube walls. What is the possibility of loosening of the SGIFR assemblies over time? NuScale Nonproprietary NuScale Nonproprietary

Response

The steam generator inlet flow restrictor (SGIFR) design and installation precludes potential for mechanical loosening. (( }}2(a),(c),ECI Therefore, the SGIFR assembly is not expected to loosen over time. No changes to the SDAA are necessary. NuScale Nonproprietary NuScale Nonproprietary}}