ML23181A028
| ML23181A028 | |
| Person / Time | |
|---|---|
| Issue date: | 09/13/2023 |
| From: | Joseph Sebrosky NRC/NRR/DANU/UARP |
| To: | Steven Lynch Office of Nuclear Reactor Regulation |
| References | |
| Download: ML23181A028 (1) | |
Text
September 13, 2023 MEMORANDUM TO:
Steven Lynch, Chief Advanced Reactor Policy Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation FROM:
Joseph M. Sebrosky, Senior Project Manager Advanced Reactor Policy Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MAY 11, 2023, PUBLIC MEETING TO DISCUSS TECHNOLOGY INCLUSIVE MANAGEMENT OF SAFETY CASE On May 11, 2023, the U.S. Nuclear Regulatory Commission (NRC) staff held a public meeting with stakeholders to discuss the technology inclusive management of safety case (TIMaSC) industry initiative. The meeting notice is available in the NRCs Agencywide Documents Access and Management System (ADAMS) at Accession No. ML23131A007, and the presentation slides are available at ADAMS Accession No. ML23130A294. The enclosure to this summary provides the attendees for the meeting as captured by Microsoft Teams.
The purpose of the meeting was for industry to outline its plans to develop TIMaSC. The purpose of TIMaSC would be to develop an endorsable guidance document for the management of a licensing modernization project (LMP) based safety case. Industry envisions TIMaSC would be used by licensees that follow the guidance in the following documents:
Nuclear Energy Institute (NEI) 18-04, Revision 1, Risk-Informed Performance-Based Technology Guidance for Non-Light Water Reactors, ADAMS Accession No. ML19241A336.
NEI 21-07, Revision 1, Technology Inclusive Guidance for Non-Light Water Reactor Safety Analysis Report: for Applicants Utilizing NEI 18-04 Methodology, ADAMS Accession No. ML22060A190. This guidance is referred to as technology inclusive content of application project (TICAP) guidance.
NEI 22-05, Revision A, Technology Inclusive Risk Informed Change Evaluation (TIRICE). This is currently a draft document that is part of a separate discussion with industry. NRC staff comments on this version of the document can be found at ADAMS Accession No. ML23107A257.
CONTACT: Joseph Sebrosky, NRR/DANU 301-415-1132 Joseph M.
Sebrosky Digitally signed by Joseph M. Sebrosky Date: 2023.09.13 11:06:52 -04'00'
S. Lynch 2
Meeting Highlights Industry noted that during the development of NEI 18-04, NEI 21-07, and NEI 22-05, it identified the need to develop additional guidance related to the maintenance of the safety case. Examples where additional guidance would be beneficial include:
o Operating experience indicates reliability or capability targets for safety significant structures, systems, and components (SSCs) are not met o Operating experience indicates reliability or capability targets for safety significant SSCs have more than anticipated margin o Results of tests, experiments, and analyses o Management of the safety case as it relates probabilistic risk assessment (PRA) changes and programs to control the PRA Industrys proposed timeline included development of the guidance in the 2024 timeframe including tabletop exercises, with the NRC endorsement in the 2025 timeframe.
The NRC staff noted that the development of TIMaSC guidance appeared to be appropriate and that further interactions on the effort would be beneficial. The NRC staff posed questions regarding the scope of TIMaSC that could be considered as the effort moves forward including:
o Whether TIMaSC could be used during the operational phase as part of the significance determination process (SDP). The SDP is the process used by the NRC staff to evaluate inspection findings to determine their safety significance. This involves assessing how the inspection findings affect the risk of a nuclear plant accident, either as a cause of the accident or the ability of plant safety systems or personnel to respond to the accident.
o Whether TIMaSC could be included as part of programs that are described in Chapter 8 of NEI 21-07.
o Whether the PRA periodic upgrade regulatory requirements in Title 10 of the Code of Federal regulations (10 CFR) Part 50 (i.e., 50.71(h)) and those PRA upgrade provisions in the ongoing 10 CFR Part 50 and 52 alignment rulemaking would be considered as part of the scope of TIMaSC.
Enclosure:
Attendance List
NRC-001 OFFICE NRR/DANU/UARP/PM NRR/DANU/UARP/BC NRR/DANU/UARP/PM NAME JSebrosky SLynch JSebrosky DATE 9/13/2023 9/13/2023 9/13/2023 Enclosure May 11, 2023, Public Meeting to Discuss Technology Inclusive Management of Safety Case Attendance List*
NAME AFFILIATION NAME AFFILIATION John Segala NRC/NRR/DANU Brandon Chisholm Southern Company Martin Stutzke NRC/NRR/DANU Ben Holtzman Nuclear Energy Institute (NEI)
Nan Valliere NRC/NRR/DANU Steven Nesbit LMNT Consulting William Reckley NRC/NRR/DANU/UARP Karl Fleming KNF Consulting Amy Cubbage NRC/NRR/DANU/UARP Ingrid Nordby X-energy Joe Sebrosky NRC/NRR/DANU/UARP Steve Vaughn X-energy James ODriscoll NRC/NRR/DANU/UARP Amanda Spalding Westinghouse Scott Tonsfeldt NRC/NRR/DANU/UARP Dave Grabaskas Argonne National Lab Ian Jung NRC/NRR/DANU/UTB1 Rob Burg NA Michelle Hart NRC/NRR/DANU/UTB2 Jason Andrus NA Michael Orenak NRR/NRR/DANU/UAL1 Svetlana Lawrence NA Jim Kinsey INL Keeshia B.
Goodenough NA Chris Chwasz INL Steven Pope NA Tom King INL Barton Landon Pate NA Tom Hicks INL Mihaela Biro NA Paul Santamaura NA
- Attendance list based on Microsoft Teams Participant list. List does not include two individuals that connected via phone.