ML24215A097

LLC, Response to SDAA Audit Question Number A-4.Fluence.TeR-5

ML24215A097
Person / Time
Site:	05200050
Issue date:	08/02/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
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Download: ML24215A097 (1)

Text

Response to NuScale Technical Report Audit Question Question Number: A-4.Fluence.TeR-5 Receipt Date: 09/15/2023 Question:

Revise TR-118976-P to explicitly state that (( 2(a),(c),ECI Provide markups. The response to audit item A-Fluence.TeR-1 states that the (( }} 2(a),(c),ECI However, the conclusion on page 29 of the TR-118976-P states: The peak RPV beltline surface and CNV beltline at 1/4-T fluence over a 60-year NPM operating life (assumed 95 percent capacity factor) is calculated to be (( }} 2(a),(c),ECI. This statement could cause confusion because it can be read as the (( }} 2(a),(c),ECI

Response

During the clarification call on this audit question on October 17, 2023, the NRC staff indicated that (( }}2(a),(c),ECI on page 30 of TR-118976-P removes the confusion. The attached markup changes the wording as agreed in Section 6.0 of TR-118976-P. Markups of the affected changes, as described in the response, are provided below: NuScale Nonproprietary NuScale Nonproprietary

Fluence Calculation Methodology and Results TR-118976-NP Draft Revision 1 © Copyright 2023 by NuScale Power, LLC 29 6.0 Summary and Conclusions A best-estimate neutron fluence calculation for the NPM is performed using of the MCNP6 code based on RG 1.190. Alternatives to particular RG 1.190 regulatory positions are provided in Appendix C. Biases and uncertainties associated with the MCNP6 best-estimate neutron fluence model are reported in Table 4-1, which are established through benchmarking against the VENUS-3 experiment and NPM-specific sensitivity studies associated with key MCNP6 modeling simplifications and inputs. Audit Question A-4.Fluence.TeR-5 The peak RPV beltline surface and CNV beltline at 1/4-T fluence over a 60-year NPM operating life (assumed 95 percent capacity factor) is calculated to be (( }}2(a),(c), as reported in Table 5-1. Neutron fluence estimates provided in this report are acceptable for supporting Final Safety Analysis Report Section 4.3 for the US460 standard design and meet the regulatory guidance and requirements discussed in Section 2.1 of this report.}}