ML24215A028

LLC, Response to Sdaa Audit Question Number A-3.7.2-23

ML24215A028
Person / Time
Site:	05200050
Issue date:	08/02/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
LO-169995
Download: ML24215A028 (1)

Text

Response to SDAA Audit Question Question Number: A-3.7.2-23 Receipt Date: 08/21/2023 Question:

(Follow-on from A-3.7.2-6). Staff finds the applicant's response to Audit Question A-3.7.2-6 is accetable; however, a key summary of the response should be included in FSAR Section 3.7.2.1.2.2 to support staff's safety evaluation. The following or similar statement can be considered for inclusion in the FSAR: "The simplified CNV model used in the RXB seismic analysis is developed to capture the overall dynamic behavior of a more detailed CNV model used in the NPM seismic analysis addressed in NuScale Technical Report, TR-121515."

Response

The current content of the US460 Standard Design Approval Application (SDAA) Section 3.7.2 meets the Design Specific Review Standard (DSRS) 3.7.2. The compatibility of the simplified NuScale Power Module (NPM) model with the detailed NPM model is verified through modal analysis showing the similarity of the major modes of the two models. The simplified NPM model used in the Reactor Building (RXB) seismic analysis is developed to capture the dynamic behavior of a detailed NPM model used in the seismic analysis addressed in NuScale Technical Report, TR-121515-P, US460 NuScale Power Module Seismic Analysis.

No changes to the SDAA are necessary.

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