ML25324A315
| ML25324A315 | |
| Person / Time | |
|---|---|
| Site: | 99902041 |
| Issue date: | 11/24/2025 |
| From: | Ngola Otto Licensing Processes Branch |
| To: | Framatome |
| Shared Package | |
| ML25324A316 | List: |
| References | |
| Download: ML25324A315 (0) | |
Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION 1
OFFICIAL USE ONLY - PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION (RAI)-10923 BY THE OFFICE OF NUCLEAR REACTOR REGULATION TOPICAL REPORT ANP-10323, REVISION 1, SUPPLEMENT 1P, REVISION 0, ONE GALILEO: FUEL ROD THERMAL-MECHANICAL FUEL ROD METHODOLOGY FOR PRESSURIZED WATER REACTORS FRAMATOME, INC.
DOCKET NO. 99902041 ISSUE DATE: 11/24/2025
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Background===
By letter dated April 1, 2025 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML25092A022), Framatome Inc., submitted topical report (TR) ANP-10323, Revision 1, Supplement 1P, Revision 0, One GALILEO Fuel Rod Thermal-Mechanical Methodology for Pressurized Water Reactors, for U.S. Nuclear Regulatory Commission (NRC) review and approval. The NRC staff reviewed the proposed TR, conducted an audit (ML25210A207), and determined that additional information is needed to complete the review. The NRC staffs request for additional information (RAI)-10923 is provided below.
Regulatory Basis Regulatory guidance for the review of fuel system materials and designs and adherence to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criteria (GDC)-10, Reactor Design, GDC-27, Combined Reactivity Control Systems Capability, GDC-28, Reactivity Limits, and GDC-35, Emergency Core Cooling, are provided in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (SRP), Section 4.2, Fuel System Design. In accordance with SRP Section 4.2, the objectives of the fuel system safety review are to provide reasonable assurance that: (1) the fuel system is not damaged as a result of normal operation and anticipated operational occurrences (AOOs), (2) fuel system damage is never so severe as to prevent control rod insertion when it is required, (3) the number of fuel rod failures is not underestimated for postulated accidents, and (4) coolability is always maintained. A not damaged fuel system is defined as fuel rods that do not fail, fuel system dimensions that remain within operational tolerances, and functional capabilities that are not reduced below those assumed in the safety analysis. Objective 1, above all, is consistent with GDC-10, and the design limits that accomplish this are called specified acceptable fuel design limits. Fuel rod failure means that the fuel rod leaks, and that the first fission product barrier (the cladding) has, therefore, been breached. However, the NRC staff recognizes that it is not possible to avoid all fuel rod failures during normal operation, and reactor coolant cleanup systems are installed to deal with a small number of leaking rods.
Question 1 Section 4.0, Rod Internal Pressure and Cladding Oxide Thickness, of TR ANP-10323, Revision 1, Supplement 1P, Revision 0, states that ((
)). To understand the power histories that are
ML25324A316 (Package)
ML25324A314 (RAI Question - Proprietary)
ML25324A315 (RAI Question - Non-Proprietary)
OFFICE NRR/DSS/SFNB/BC NRR/DORL/LLPB/PM NRR/DORL/LLPB/BC NAME SKrepel NOtto JRankin DATE 09/22/2025 11/19/2025 11/19/2025 OFFICE NRR/DORL/LLPB/LA NRR/DORL/LLPB/PM NAME DHarrison NOtto DATE 11/21/2025 11/24/2025