ML24346A320
| ML24346A320 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 12/11/2024 |
| From: | NuScale |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24346A130 | List:
|
| References | |
| LO-175762 | |
| Download: ML24346A320 (1) | |
Text
Response to SDAA Audit Question Question Number: A-19.1-62 Receipt Date: 04/22/2024 Question:
FSAR Section 19.1.6.1.3 discusses module drop scenarios and concludes that the offsite dose consequences of core damage in a horizontal module with a damaged containment vessel results in a radionuclide release that is a fraction of that associated with a large release.
NuScale is requested to provide a summary of the methodology, assumptions, and results (i.e.,
offsite dose consequences) for the module drop scenarios. The summary should identify any differences compared to the DCA and the impact of these differences on the conclusions for the SDAA compared to the DCA.
Response
ER-126919, Dropped Module Consequence Analysis, Revision 0, which is available in the SDAA Audit Section 19.1-19.3 eRR, evaluates the NuScale Power Module (NPM) drop event for the US460 Standard Design Approval Application (SDAA). The evaluation consists of a comparison between the US600 and US460 designs in aspects that are relevant to the NPM drop event, and identifies four relevant design changes from the US600 design: (1) the core power is increased, (2) the number of reactor vent valves is decreased, (3) the reactor pool depth is reduced, and (4) ((2(a),(c) The evaluation concludes that the US460 NPM drop event does not result in a large release. ((
}}2(a),(c)
No changes to the SDAA are necessary. NuScale Nonproprietary NuScale Nonproprietary}}