ML25160A110
| ML25160A110 | |
| Person / Time | |
|---|---|
| Site: | 99902041 |
| Issue date: | 06/13/2025 |
| From: | Ngola Otto Licensing Processes Branch |
| To: | Framatome |
| References | |
| Download: ML25160A110 (1) | |
Text
1 REQUEST FOR ADDITIONAL INFORMATION (RAI)-10637 BY THE OFFICE OF NUCLEAR REACTOR REGULATION ANP-10357P, REVISION 0, TXS COMPACT PLATFORM TOPICAL REPORT FRAMATOME INC.
DOCKET NO. 99902041 ISSUE DATE: 06/13/2025
=
Background===
By letter dated August 2, 2024 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML24218A279), Framatome, Inc. (Framatome) submitted ANP-10357P, Revision 0, TXS Compact Platform Topical Report (TR) for U.S. Nuclear Regulatory Commission (NRC) staffs review and approval. The NRC staff has reviewed the proposed TR, conducted an audit (ADAMS Accession No. ML24352A156), and determined that additional information is needed to complete the review. The NRC staffs request for additional information (RAI)-10637 is provided below.
Regulatory Basis The regulatory basis for this RAI can be found in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(h) which incorporates the requirements of Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 603-1991, Criteria for Safety Systems for Nuclear Power Generating Stations, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities," and Regulatory Guide (RG) 1.75, Criteria for Independence of Electric Safety Systems.
Question 1 The regulation at 10 CFR 50.55a(h) incorporates by reference the requirements of IEEE Std. 603-1991, Criteria for Safety Systems for Nuclear Power Generating Stations, and the correction sheet dated January 30,1995. Clause 5.4, Equipment Qualification, of IEEE Std. 603-1991 requires, in part, that safety system equipment shall be qualified by type test, previous operating experience, or analysis, or any combination of these three methods, to substantiate that it will be capable of meeting, on a continuing basis, the performance requirements as specified in the design basis.
As part of the equipment qualification, the Class 1E to non-Class 1E isolation qualification testing shall be performed. The regulatory guidance on the Class 1E to non-Class 1E isolation testing is included in RG 1.75, and Section 6.3.6 of EPRI TR-107330, Requirements Compliance Traceability Matrix, as endorsed in RG 1.209, "Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants."
2 However, the NRC staff found that Class 1E to non-Class 1E isolation qualification testing has not been addressed in the submitted TXS COMPACT TR. The NRC staff requests that the application provides additional information to substantiate compliance with the regulatory requirement on the qualification of the Class 1E to non-Class 1E isolation for the TXS COMPACT Platform.
ADAMS Accession No.: ML25160A110 (RAI - Non-Proprietary)
OFFICE NRR/DORL/LLPB/PM NRR/DORL/LLPB/LA NRR/DEX/EICB/BC NAME NOtto DHarrison FSacko DATE 6/11/2025 6/11/2025 6/12/2025 OFFICE NRR/DORL/LLPB/BC NRR/DORL/LLPB/PM NAME JRankin NOtto DATE 6/13/2025 6/13/2025