ML25069A641

Response to NuScale Topical Report Audit Question Number: A-FSR.LTR-46

ML25069A641
Person / Time
Site:	05200050
Issue date:	03/10/2025
From:	NuScale
To:	Office of Nuclear Reactor Regulation
Shared Package
ML25069A609	List: ML25069A610 ML25069A611 ML25069A613 ML25069A614 ML25069A616 ML25069A628 ML25069A630 ML25069A632 ML25069A634 ML25069A636 ML25069A641 ML25069A643 ML25069A645 ML25069A648 ML25069A650 ML25069A659 ML25069A661 ML25069A662 ML25069A663 ML25069A665
References
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Download: ML25069A641 (1)

Text

Response to NuScale Topical Report Audit Question Question Number: A-FSR.LTR-46 Receipt Date: 10/14/2024 Question:

Section 6.5.3.3: System Bias for Damaged Fuel Cladding states, A damaged FA is assumed to have lost cladding integrity such that the fuel pellet to clad gap is completely flooded with moderator for all fuel pins. Does the analysis consider other types of damaged FA, e.g. FA with empty lattices?

Response

The analysis does not consider other types of damaged fuel assemblies, such as missing fuel pins or fuel pins replaced with an inert rod. It is the responsibility of the licensee to assess such conditions in accordance with 10 CFR 50.59, if they occur.

No changes to the LTR are necessary.

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