ML25069A613
| ML25069A613 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 03/10/2025 |
| From: | NuScale |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML25069A609 | List: |
| References | |
| LO-180139 | |
| Download: ML25069A613 (1) | |
Text
Response to NuScale Topical Report Audit Question Question Number: A-FSR.LTR-11 Receipt Date: 05/10/2024 Question:
The analysis states that damaged FA is assumed to have the pellet-clad gap flooded with moderator. Provide additional clarification on what is meant by damaged fuel assemblies. The extent of damage and the extent of damage to fuel located in the FSR.
Response
Section 6.5.3.3 and Section 6.5.6 provide additional details about the modeling assumptions for damaged fuel assemblies. A damaged fuel assembly is modeled assuming the loss of cladding integrity of all fuel rods, such that the gap between the fuel pellet and cladding is filled with water. Damaged fuel assemblies are assumed to be new, unirradiated fuel assemblies and are restricted to storage locations intended for new fuel assemblies.
No changes to the LTR are necessary.
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