ML23060A094
| ML23060A094 | |
| Person / Time | |
|---|---|
| Issue date: | 10/30/2023 |
| From: | Lois James Licensing Processes Branch |
| To: | Gerond George Licensing Processes Branch |
| Shared Package | |
| ML23011A341 | List: |
| References | |
| EPID L-2023-TOP-0018 | |
| Download: ML23060A094 (1) | |
Text
OFFICIAL USE ONLY PROPRIETARY INFORMATION Enclosure 1 OFFICIAL USE ONLY PROPRIETARY INFORMATION U.S. Nuclear Regulatory Commission Public Meeting Summary
Title:
Pre-application Meeting for Submittal of a Revision to BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel (SS) for Boiling Water Reactor (BWR) Core Shrouds Date of Meeting:
February 27, 2023, 2:00 pm - 3:30 pm Location:
Webinar Type of Meeting:
This was a closed meeting. It contained trade secrets and commercial or financial information (proprietary information).
Purpose of the Meeting:
To provide the U.S. Nuclear Regulatory Commission (NRC) staff with an introduction to the upcoming submittal of a revision to BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated SS for BWR Core Shrouds.
General Details:
The NRC staff held a closed meeting with Electric Power Research Institute (EPRI) representatives to provide the NRC staff with an introduction to the upcoming submittal of a revision to BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated SS for BWR Core Shrouds. The meeting began at 2:00 pm and ended at 3:30 pm. There were fourteen NRC staff members, three EPRI representatives, and seven EPRI-industry members.
The meeting began with introductions of the NRC staff and EPRI representatives. No members of the public were in attendance due to the proprietary nature of the discussion.
Summary of Meeting:
The EPRI representatives began their presentation by explaining that new irradiated SS data has been introduced to BWRVIP-100, Revision 2.
Most of the new irradiated data comes from Zorita core barrel and baffle plate (weld, base metal, and heat affected zone (HAZ)) and Barsebck Unit 2 core shroud weld which are documented in:
BWRVIP-294, Revision 2: BWR Vessel and Internals Project: Fracture Toughness of Zorita RPV Core Internals Applicable to BWRs: Final Report 2019. EPRI, Palo Alto, CA: 2019, 3002015929.
Materials Reliability Program: Zorita Internals Research Project (MRP-440), Testing of Highly-Irradiated Baffle Plate Material. EPRI, Palo Alto, CA: 2019, 3002016015.
Materials Reliability Program: Fluence Effects on Stainless Steel Welds (MRP-451):
Crack Growth Rate and Fracture Toughness Testing of Zorita Weld and HAZ Materials.
EPRI, Palo Alto, CA: 2020, 3002018250.
Chen, Y., Alexandreanu, B., Natesan, K., Crack Growth Rate and Fracture Toughness Tests on Irradiated Ex-Plant Materials, ANL 19-45, Argonne National Laboratory, July 2020.
NUREG/CR-7027, ANL-10/11, Degradation of LWR Core Internal Materials Due to Neutron Irradiation, December 31, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110100377).
OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION The NRC staff asked if the flaw analysis software was also being updated based on BWRVIP-100, Revision 2. The EPRI representatives stated that the software is being updated and would be available later in calendar year 2023. The NRC staff noted that the software based on BWRVIP-100, Revision 2, would be available for industry use and potentially for the basis of license amendments submitted to the staff before BWRVIP-100, Revision 2, has been reviewed and approved by the staff. The EPRI representatives said that they will need to consider this comment and how to continue with the development of the software and how to roll it out for industry use.
Based on the presentation, the NRC staff noted that it does not appear that the revisions for BWRVIP-100, Revision 2, impact the fluence methodology. The EPRI representatives confirmed this statement.
Regarding EPRIs desire for a final SE to be issue by December 2024, the NRC staff noted that this is about 2 months short of a standard schedule. The NRC staff stated that it understands EPRIs desire to have a final SE by the end of 2024 and will work with all parties (NRC staff, the Advisory Committee on Reactor Safeguards, and EPRI) to try to meet the requested goal.
Public Participation Themes:
Due to the proprietary nature of the material discussed, no members of the public were in attendance.
Action Items/Next Steps:
The NRC staff will prepare and issue a meeting summary.
Attachments:
Meeting description and agenda - ADAMS Accession No. ML23012A334 (public)
NRC slide presentation - ADAMS Accession No. ML22335A536 (public)
Vendor slide presentation - ADAMS Accession No. ML23048A259 (public)