ML24346A193

LLC - Response to SDAA Audit Question Number A-4.FuelCR.TeR-3

ML24346A193
Person / Time
Site:	05200050
Issue date:	12/11/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
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Text

Response to NuScale Technical Report Audit Question Question Number: A-4.FuelCR.TeR-3 Receipt Date: 02/26/2024 Question:

Table 4-2 of TR-117605-P shows very little margin in 3rd category. Revise the TeR and provide a markup to include a list of the uncertainties that have been applied in this calculation and justification for the uncertainties such that a high confidence can be demonstrated that this limit will not be exceeded.

Response

Table 1 provides a summary of the conservatisms used in the NuScale cladding stress analysis.

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] Exceeding the margin for cladding stress during operation is not a concern because the margin improves with increasing burnup.

To be consistent with the other evaluations provided in TR-117605-P, Revision 1, NuFuel-HTP2' Fuel and Control Rod Assembly Designs, and with the US600 equivalent technical report, TR-0816-51127, Revision 3, NuFuel-HTP2' Fuel and Control Rod Assembly Designs, a markup of TR-117065-P including Table 1 is not provided.

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]

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Response Supplement TR-117605-P, Revision 1, NuFuel-HTP2'Fuel and Control Rod Assembly Designs will not be updated to include Table 1. The following is an excerpt from Section 4.2.4.1.1 of the Safety Evaluation Report for FSAR Chapter 4 from the Design Certification Application (ML20205L411) regarding the cladding stress analysis with emphasis in bold:

Section 4.1.1, Stress and Loading Limits, of TR-0816-51127, Revision 3, provides a stress and loading analysis. The shipping and handling stress analysis and the fuel assembly/component stress analysis were performed in accordance with EMF 116(P)(A), Generic Mechanical Design Criteria for PWR Fuel Designs, Revision 0, issued February 1999 (ADAMS Accession No. ML003681173), and the clad stress analysis and the cladding buckling analysis were performed in accordance with BAW-10227P-A, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, Revision 1, issued June 2003 (ADAMS Accession No. ML15162B043). The staff finds that these analyses demonstrate the calculated stresses and that loadings are all within the design criteria for all required conditions.

The conclusions outlined in the SER above did not require the analysis conservatisms in Table 1 to be incorporated into TR-0816-51127, Revision 3; these conclusions are still applicable to TR-117605-P Revision 0.

No changes to the SDAA are necessary.

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