ML23184A085
| ML23184A085 | |
| Person / Time | |
|---|---|
| Site: | 99901469 |
| Issue date: | 07/26/2023 |
| From: | Michael Orenak NRC/NRR/DANU/UAL1 |
| To: | Jessup W NRC/NRR/DANU/UAL1 |
| References | |
| EPID L-2022-LRM-0069 | |
| Download: ML23184A085 (1) | |
Text
OFFICAL USE ONLY PROPRIETARY INFORMATION OFFICAL USE ONLY PROPRIETARY INFORMATION July 26, 2023 MEMORANDUM TO:
William Jessup, Chief Advanced Reactor Licensing Branch 1 Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation FROM:
Michael Orenak, Project Manager /RA/
Advanced Reactor Licensing Branch 1 Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE JUNE 6, 2023, PARTIALLY CLOSED MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND BWXT ADVANCED TECHNOLOGIES, INC. TO PROVIDE AN UPDATE ON THE BWXT ADVANCED NUCLEAR REACTOR Meeting Information:
Applicant: BWXT Advanced Technologies, Inc. (BWXT)
Docket/Project No. 99901469 EPID: L-2022-LRM-0069 Meeting
Title:
Update on BWXT BANR reactor Meeting Type: Partially Closed Public Meeting Notice Agencywide Documents Access and Management System (ADAMS):
ML23157A017 Open Portion Industry Slides: ML23156A226 Closed Portion Non-proprietary Slides: ML23143A380 Closed Portion Proprietary Slides: ML23143A381 Meeting Attendees: See Enclosure for list of meeting attendees.
OFFICAL USE ONLY PROPRIETARY INFORMATION OFFICAL USE ONLY PROPRIETARY INFORMATION Meeting Summary:
The U.S. Nuclear Regulatory Commission (NRC) staff held a partially closed in-person meeting with representatives from BWXT Advanced Technologies, Inc. (BWXT). This meeting was for BWXT to provide an update on the development of the BWXT Advanced Nuclear Reactor (BANR).
During the open portion of meeting, BWXT representatives presented their slides that described the progress in the development of the BANR reactor.
The first discussion occurred on Slide 8 regarding the use of matrix powder. The NRC staff asked where the powder is used (e.g., around the fuel or other locations). BWXT answered that they are still working on exactly where the powder will be used.
For slide 13, the NRC staff stated that Regulatory Guide 1.203, Transient and Accident Analysis Methods, (ML053500170) provides guidance for a fuel evaluation model framework.
NRC staff clarified that that the more information and context regarding scope provided to the NRC in the planned fuel qualification topical report, the easier it is to develop a safety evaluation.
The NRC staff asked if there are other long-lead time structures, systems, or components (SSCs) for the BANR reactor that may need similar white papers that are submitted for NRC comments. BWXT responded that their U.S. Department of Energy Advanced Reactor Demonstration Program award focuses on the reactor core. BWXT looked at reactivity control and other SSCs and found some may need NRC review through white papers or topical reports, but BWXT has not yet made that determination. The NRC staff commented that early engagement with the NRC is very important for these long-lead items.
The NRC staff asked why BWXT has decided to pursue uranium nitride (UN) instead of the uranium oxycarbide (UCO) used in the Advanced Gas Reactor (AGR) TRISO fuel design.
BWXT answered that it has higher fuel density (and therefore allows for higher power density or longer core life) than AGR TRISO. BWXT stated they understood that this means that there will be a gap from the AGR data sets and that gap will need to be bridged with testing or additional information for any future license applications.
There were no public comments during the public comment period.
During the closed (i.e., non-public) portion of the meeting, several discussions arose. On slide 3, the NRC staff asked what tools and figures of merit BWXT was using to develop their design.
BWXT stated that they ((
)).
On slide 5, the NRC staff asked is there any overcoat for the fuel particle, or any plans to do so.
BWXT responded ((
)).
For slide 8, the NRC staff stated that to achieve long core life, burnable poisons were likely to be needed. The NRC staff asked if a burnable poison will be used. BWXT responded ((
OFFICAL USE ONLY PROPRIETARY INFORMATION OFFICAL USE ONLY PROPRIETARY INFORMATION
)). The NRC staff then asked how close to the maximum packing fraction is the fuel. BWXT responded that the packing fraction ((
)).
For slide 11, BWXT commented that their complex fuel geometries can be a challenge for qualification due to the difficulties in analyzing those geometries.
For slide 14, the NRC staff commented that accelerated fuel qualification has a different definition for different entities. If there is a clear path for BWXT to demonstrate that fuel under accident conditions operates as designed, that would be the preferred approach.
For slide 21, the NRC staff commented that an over reliance on analysis codes can occur. Data should back up a fuel safety determination.
For slide 23, the NRC staff noted that the Transformational Challenge Reactor tests at the Massachusetts Institute of Technology released fission gas from one of the test capsules. The NRC staff asked if BWXT is aware of this experience and whether they are taking it into account for their design. BWXT responded that one specific test contained an unusual result. BWXT is looking at how to de-risk their fuel design for this issue and gather additional information as the test results are assessed.
The NRC staff asked if there is a plan to retain parts of the fuel for subsequent testing for safety (e.g., water or air ingress, higher temperatures etc.). BWXT responded that they have plans to do so.
For slide 25, the NRC staff commented that transient testing is needed for fuel qualification.
Due to BWXTs ((
)).
For slide 27, the NRC staff asked what factor of scaling BWXT is planning to use. BWXT responded ((
)).
((
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CONTACT: Michael Orenak, NRR/DANU (301) 415-3229
OFFICAL USE ONLY PROPRIETARY INFORMATION OFFICAL USE ONLY PROPRIETARY INFORMATION
SUBJECT:
SUMMARY
OF THE JUNE 6, 2023, PARTIALLY CLOSED MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND BWXT ADVANCED TECHNOLOGIES, INC. TO PROVIDE AN UPDATE ON THE BWXT ADVANCED NUCLEAR REACTOR DATED: JULY 26, 2023 DISTRIBUTION:
Public RidsOgcMailCenter RidsOpaMail Resource RidsNrrDanu Resource RidsNrrDanuUarp Resource MOrenak, NRR BTravis, NRR DBeacon, NRR GOberson, NRR WJessup, NRR ADAMS Accession Number: ML23184A085 NRR-052 OFFICIAL RECORD COPY OFFICE NRR/DANU/UAL1/
PM NRR/DANU/UAL1/
BC NRR/DANU/UAL1/PM NAME MOrenak WJessup MOrenak DATE 7/3/2023 7/26/2023 7/26/2023
Enclosure List of Attendees Observation meeting between the U.S. Nuclear Regulatory Commission Staff and BWXT Regarding an Update to the BANR Tuesday, June 6, 2023 Name Organization Mike Orenak U.S. Nuclear Regulatory Commission (NRC)
Boyce Travis NRC Dan Beacon NRC Greg Oberson NRC Abbey Donahue BWX Technologies, Inc. (BWXT)
Alex Shrier BWXT Don Statile BWXT Jeff Powers BWXT Michael Haggerty BWXT Neil Herman BWXT Jana Bergman Curtiss-Wright Matt Marzano US Senate Environment and Public Works Committee Andrea Janeth Platts News