ML24348A073

Response to NuScale Topical Report Audit Question Number A-NonLOCA.LTR-57

ML24348A073
Person / Time
Site:	05200050
Issue date:	12/13/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
LO-176318
Download: ML24348A073 (1)

Text

Response to NuScale Topical Report Audit Question Question Number: A-NonLOCA.LTR-57 Receipt Date: 06/28/2024 Question:

FSAR Section 15.2.7 describes three different event sequences, (i.e., pump failures, valve malfunctions, and loss of AC), for the loss of FW flow event. However, there is no discussion of the three potential initiating events and their sequences in the TR. As discussed in FSAR Section 15.2.7.2, these events establish the limiting case for peak RCS pressure, peak SG pressure, and minimum MCHFR respectively. Please revise TR Section 7.2.10 to include discussions of the three event sequences to make the TR consistent with FSAR Section 15.2.7 analyses.

Please provide proposed markup to the TR.

Response

This audit question requesting update to Section 7.2.10 is the same as audit question A-NonLOCA.LTR-39. The audit question A-NonLOCA.LTR-39 was sent to NuScale on May 10, 2024, responded to by NuScale on May 15, 2024, and closed by the NRC on June 6, 2024.

Because this issue has already been raised, responded to, and resolved, no further response is necessary. See the response to audit question A-NonLOCA.LTR-39 for more information.

No changes to the SDAA are necessary.

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