ML24317A246
| ML24317A246 | |
| Person / Time | |
|---|---|
| Site: | 99902041 |
| Issue date: | 11/21/2024 |
| From: | Ngola Otto Licensing Processes Branch |
| To: | Gerond George Licensing Processes Branch |
| References | |
| EMF-93-177, EPID L-2024-LRM-0118 | |
| Download: ML24317A246 (1) | |
Text
November 21, 2024 MEMORANDUM TO: Gerond A. George, Chief Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Ngola A. Otto, Project Manager /RA/
Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF NOVEMBER 7, 2024, PRE-SUBMITTAL MEETING WITH FRAMATOME INC. AND THE U.S. NUCLEAR REGULATORY COMMISSION FOR TOPICAL REPORT, EMF-93-177, REVISION 1, SUPPLEMENT 3, ATRIUM BOILING WATER REACTOR ENHANCED ACCIDENT MODEL (A-BEAM) (EPID L-2024-LRM-0118)
On November 7, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff held a partially closed meeting via Microsoft Teams with representatives from Framatome Inc. (Framatome).
The purpose of this meeting was for the NRC staff to hold pre-submittal discussions for Framatome EMF-93-177, Revision 1, Supplement 3, ATRIUM BWR [Boiling Water Reactor]
Enhanced Accident Model (A-BEAM), topical report (TR). The meeting notice dated October 17, 2024, and all associated information are available in the Agencywide Documents Access and Management System (ADAMS) at Package Accession No. ML24310A247. An initial pre-submittal meeting was held on November 19, 2020 (ADAMS Accession No. ML20353A199).
During the open session, the Framatome representative provided a high-level overview of the EMF-93-177, Revision 1, Supplement 3 and description of planned changes. EMF-93-177, Revision 1, Mechanical Design for BWR Fuel Channels, dated January 14, 2005 (ADAMS Accession No. ML050240012) is the base TR that was approved by the NRC staff. The Framatome representatives also explained that EMF-93-177, Revision 1, Supplement 3 provides an option for a more detailed horizontal dynamic model to get more refined accident analysis results for fuel assembly components. In addition, the Framatome representatives explained that Supplement 3 does not include any changes in the TR related to the fuel channel design, design criteria, or normal operation analysis methods. During the closed session, the Framatome representatives, provided details on ATRIUM BWR A-BEAM, Spacer Grid Benchmark, Fluid Structure Interaction, and KWUSTOSS Sample Problem.
CONTACT: Ngola Otto, NRR/DORL 301-415-6695
The Framatome representatives also addressed several NRC staff questions focused on the technical content of and motivation for the supplement, justifications for modeling decisions, test component design and material properties, and the setup of test facilities. In closing, Framatome representatives highlighted next steps and schedule for the planned submittal.
Docket No. 99902041
Enclosure:
List of Attendees
Enclosure List of Attendees Partially - Closed Meeting between Framatome Inc.
and the U.S. Nuclear Regulatory Commission on Topical Report EMF-93-177, Revision 1, Supplement 3, Atrium BWR Enhanced Accident Model November 7, 2024 9:00 am - 11:30 am NAME ORGANIZATION Morris Byram Framatome Inc. (Framatome)
Brett Matthews Framatome Scott Adair Framatome Szilard Kovacs Framatome Benoit Dulauroy Framatome Keziah Hampton Framatome Jeff Morris Framatome Demetrius Murray U. S. Nuclear Regulatory Commission (NRC)
Patrick Raynaud NRC Gerond George NRC Ngola Otto NRC Alex Collier NRC
ML24310A247 (Package)
ML24317A246 (Summary)
ML24311A052 (Open Session Presentation)
ML24310A239 (Presentation - Non-Proprietary)
ML24310A240 (Presentation - Proprietary)
- via email OFFICE DORL/LLPB/PM*
DORL/LLPB/LA*
DORL/LLPB/BC*
DORL/LLPB/PM*
NAME Notto DHarrison GGeorge NOtto DATE 11/15/2024 11/21/2024 11/21/2024 11/21/2024