ML24348A058
| ML24348A058 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 12/13/2024 |
| From: | NuScale |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24348A006 | List:
|
| References | |
| LO-176318 | |
| Download: ML24348A058 (1) | |
Text
Response to NuScale Topical Report Audit Question Question Number: A-NonLOCA.LTR-39 Receipt Date: 05/13/2024 Question:
TR Section 7.2.10 (Loss of Normal Feedwater Flow) does not include descriptions of the events that may cause loss of normal feedwater flow AOO. The scenarios should be presented as they establish the limiting case for peak RCS pressure, peak SG pressure, and minimum MCHFR.
Response
The non-loss-of-coolant accident (non-LOCA) topical report (TR-0516-49416-P, Revision 4) describes that [a] postulated fault results in a partial or complete loss of feedwater flow, and the water in the steam generators boils off in Section 7.2.10.1. Although the possible causes of the loss of feedwater flow are not described, the statement is identical to the statement in Section 7.2.10.1 of the previous revision of the non-LOCA topical report that was reviewed and approved by the NRC (TR-0516-49416-P-A, Revision 3). Because the information requested to be provided in the topical report in this audit question was not required to be included in the topical report to support the previous NRC review and approval, no changes to the topical report are required.
Note that potential causes of a loss of feedwater event are described in Final Safety Analysis Report (FSAR) Section 15.2.7.1. There is nothing specific about these potential causes that impact the methodology. Therefore, inclusion of the specific potential causes in the topical report is not necessary to describe the methodology for analyzing the event.
No changes to the SDAA are necessary.
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