ML20043F546
| ML20043F546 | |
| Person / Time | |
|---|---|
| Issue date: | 02/14/2020 |
| From: | Michelle Gonzalez, Nathan Siu NRC/RES/DRA |
| To: | |
| References | |
| Download: ML20043F546 (14) | |
Text
US NRC PRA Use and Development:
2020 Update WGRISK Annual Meeting February 26-28, 2020 Michelle Gonzalez Nathan Siu Division of Risk Analysis Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission
NRC Regulatory Process and Integrated Risk-Informed Decision-Making (RIDM)
- NRC Regulatory Process components:
- Regulatory Guidance
- Licensing, Decommissioning and Certification
- Oversight
- Operational Experience
- Support for decision-making 2
Regulatory Guides and ASME/ANS PRA Standards 3
2020 2021 RG 1.200 Rev. 3 RG 1.200 Rev. 4 ASME/ANS-RA-1.1, Level 1/LERF ASME/ANS RA-S-1.3, Level 3 ASME/ANS RA-S-1.2, Level 2 ASME/ANS RA-S-1.4, Non LWRs ASME/ANS RA-S 1.5, ALWR (for trial use)
ANS 58.22, LPSD
Regulatory Activities: Operating Reactors/ Risk Informed Licensing
- Risk-Informed Technical Specifications Completion Times
- Risk-Informed Technical Specifications (TS) extended completion times issued Revision 2 to TSTF 505 (ADAMS Accession No. ML18310A171, December 2018)
- 11 operating units have received approval to implement the program
- Other applications under review
- RG 1.177 to address Technical Specification Completion Times and limit to a maximum of 90 days
- 10 CFR 50.69: Risk-Informed Categorization and Treatment of Structures, Systems and Components
- Issued the SE for approval of the first non-pilot 50.69 application.
- Issued SEs approving the program for 25 operating units; other applications under review 4
Regulatory Activities: Operating Reactors / New and Advanced Reactors NRC and industry workshop on 50.69/4b lessons learned on January 30-31, 2019.
- Incorporating lessons learned is improving the quality of submittals and efficiency of reviews New/ Advanced Reactors NRC preparing to review the non-LWR standard in 2020.
Draft Regulatory Guide - DG 1353, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Approach to Inform the Content of Applications for Licenses, Certifications and Approvals for Non-Light Water Reactors - Published for public comment May 2019.
5
Research Activities PRA and OpE SAPHIRE and SPAR
- Continue to expand SPAR model capabilities (e.g., FLEX, IDHEAS-G ECA, etc.)
- Continue to expand detail of generic SPAR models Accident Sequence Precursor Program
- Exploring use of data analytics
- Data visualization dashboard using MS Power BI
- Use case for screening Licensee Event Reports
- NUREG/KM on Event Assessment Operating Experience
- Feasibility study on predictive maintenance 6
Research Activities: PFHA Develop tools and guidance to risk-inform new and advanced reactor design basis as well as licensing and oversight of operating reactors Collaborations
- Federal agencies (e.g., DOE Laboratories, USGS, USACE, NOAA)
- International (e.g., IRSN, NEA/WGEV)
- Industry (e.g., EPRI) 5th Annual PFHA Research Workshop
- February 19-21, 2020 @ NRC HQ (Rockville, MD)
New initiatives in 2020:
- Pilot Studies of Methods to develop full flood hazard curves
- Site-scale flooding
- Riverine flooding
- Coastal flooding 7
Research Activities: Fire PRA
- Electrical Cabinet HRRs and Fire Modeling
- NUREG-2178 vol. 1 (April 2016) & vol. 2 (mid-2020)
- Electrical Cabinet Fire Growth, Detection and Suppression Improvements-mid-2020
- Transient Fuel Package HRRs and Fire Growth
- NUREG-2232 Data Report - planned completion early 2020
- NUREG-2232 PRA Method - planned completion late 2020
- High Energy Fault (HEAF) testing
- NRC-RES working with EPRI to update HEAF Fire PRA guidance
- Full Scale Phase II OECD/NEA testing will take place 2019-2021 8
Research Activities: HRA The NRC has published RIL-2020 IDHEAS for Event and Condition Assessment HRA method and has developed its software tool.
IDHEAS-ECA is a human-centered HRA method that was specifically built to model the use of FLEX equipment and to be able to replace the agencys SPAR-H method.
The method is also capable for use in non-power reactor applications including spent fuel storage and transportation, fuel cycle facilities, nuclear medicine applications, etc.
The IDHEAS-ECA software is available free of charge for public use The NRC is working with the NEA/WGHOF to develop a new task on HRA data. It is the intent of the NRC to use data to inform and update its HRA methods (i.e. IDHEAS).
EPRI and NRC-RES have collaborated to expand upon the Fire HRA Guidelines (NUREG-1921) to address main control room abandonment (MCRA) scenarios in fire events (published by EPRI in June 2019)
MCRA HRA guidance:
Supplement 2: HRA Quantification for MCRA (published in 2019) 9
Research Activities: Level 3 PRA Status Dashboard (Updated Jan/2020) 10 Level 1 Level 2 Level 3 Reactor, at-power, internal events Complete Complete Phase 2 L3PRA management review Reactor, at-power, internal floods Complete Reactor, at-power, internal fires Phase 2 Internal technical review Phase 2 Revised model/documentation Phase 1 Initial model/documentation Reactor, at-power, seismic events Phase 2 Internal technical review Phase 2 Revised model/documentation Phase 1 Initial model/documentation Reactor, at-power, high winds Complete Phase 2 Revised model/documentation Phase 1 Initial model/documentation Reactor, at-power, other hazards Complete N/A Reactor, LPSD, internal events Phase 2 Revised model/documentation Phase 1 TAG review Phase 1 Initial model/documentation Spent fuel pool (all hazards)
Phase 1 Initial model/documentation Task has not yet begun Dry cask storage (all hazards)
Phase 1 L3PRA management review Integrated site risk (all hazards)
Phase 1 Initial model/documentation Phase 1 Phase 2 Initial model/documentation Revised model/documentation Internal technical review Internal technical review L3PRA management review L3PRA management review TAG/PWROG review Model/documentation complete
Backup Slides 11
Regulatory Guides and ASME/ANS PRA Standards
- Regulatory Guide (RG) 1.174 Rev. 3, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, January 2018
- Other RGs currently being revised for consistency with RG 1.174 Rev. 3.
- RG 1.175 Rev. 0 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing
- RG 1.177 Rev. 1 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications
- RG 1.178 Rev. 1 An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping 12
SPAR Model Status
- of Models Low Power Shut Down 8
All Hazards 23 High Winds 18 Seismic 53 Level 2 2
FLEX 66 Total of Number of Models 75 13
Additional Risk-Informed Activities
- Other risk-informed activities
- Ongoing work to develop risk tools for dry cask storage licensing
- Ongoing work to risk-inform digital I&C
- 2020 Regulatory Information Conference
- Risk Informed awareness workshop, seminars and committees
- Conducted Dynamic PSA Seminar - November 2019
- Risk management team
- Risk informed steering committee 14