ML20335A006
| ML20335A006 | |
| Person / Time | |
|---|---|
| Site: | |
| Issue date: | 12/01/2020 |
| From: | Dennis Morey Licensing Processes Branch |
| To: | Peters G Framatome ANP |
| Otto N | |
| Shared Package | |
| ML20335A004 | List: |
| References | |
| EPID L-2020-TOP-0038 | |
| Download: ML20335A006 (2) | |
Text
Enclosure AUDIT REPORT FOR FRAMATOME TOPICAL REPORT BAW-10241(P)(A), REVISION 1, ERRATA - BHTP DNB CORRELATION APPLIED WITH LYNXT TOPICAL REPORT EPID: L-2020-TOP-0038
1.0 BACKGROUND
By letter dated June 30, 2020 (Agencywide Documents Access Management System Accession No. ML20188A239), Framatome submitted a request for review and approval of BAW-10241(P)(A), Revision 1, Errata - BHTP DNB Correlation Applied with LYNXT Topical Report, a topical report (TR) which details minor changes to BAW-10241(P)(A), Revision 1.
The NRC staff will conduct this audit under the guidance provided in LIC-500 (Topical Report Process) and LIC-111 (Regulatory Audits).
The NRC staff conducted a virtual regulatory audit from August 18 through August 20, 2020, to increase review efficiency. This audit was held in accordance with the U.S. NRC, Office of Nuclear Reactor Regulation (NRR) procedure as described in LIC-111, Regulatory Audits.
2.0 REGULATORY AUDIT OBJECTIVES The objective of this audit was to increase review process efficiency through interaction with Framatomes technical experts. More specifically, the NRC staff reviewed documents and asked questions of Framatomes personnel to determine whether requests for additional information (RAI) questions were needed.
Those who participated in the audit are listed below.
Name Affiliation Joshua Kaizer NRC Reed Anzalone NRC Leslie Perkins NRC Ngola Otto NRC Gayle Elliott Framatome Buck Barner Framatome Mihnea Anghelescu Framatome John Jones Framatome Matthew Dushaw Framatome Michael Bingham Framatome Paul Whiteman Framatome 3.0 REGULATORY AUDIT BASES Regulatory guidance for the review of fuel system materials and designs and adherence to Title 10 of the Code of Federal Regulations, Appendix A to Part 50, General Design Criteria (GDC)-10, Reactor Design, GDC-27, Combined Reactivity Control Systems Capability, and GDC-35, Emergency Core Cooling, is 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.
4.0 DISCUSSION The audit consisted of a detailed walkthrough of BAW-10241(P)(A), Revision 1, Errata. The NRC staff used personal notes as well as the TR itself to practice three-way communication, explaining to Framatome their understanding of what was stated in the TR and having that understanding confirmed. The review team was able to create, complete, and concur on their draft safety evaluation by the exit of the audit.
5.0 CONCLUSION
The audit accomplished the objectives listed in Section 2.0. The NRC staff did not issue RAI questions in conjunction with this audit.