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Category:Meeting Briefing Package/Handouts
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MONTHYEARML24016A1762024-01-16016 January 2024 Integrated Safety, Security, and Safeguards Ffr Research Project ML23342A1642023-12-0808 December 2023 Networking and Information Technology Research and Development Program Software Productivity Sustainability and Quality (Spsq) NRC - Sushil Birla December 14, 2023 ML23292A0922023-10-30030 October 2023 Advanced Sensor and Instrumentation - NRC Research Status Update ML23298A0312023-10-26026 October 2023 Advanced Fuel Cycle Storage and Transportation Research ML23324A2702023-10-24024 October 2023 Session - Key Takeaways ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23275A0022023-10-0505 October 2023 Domain Modeling & Domain Engineering an Enabler for Correct-by-Construction Design ML23272A0332023-09-29029 September 2023 Identifying Hazards in a System Design ML23264A0212023-09-28028 September 2023 Addressing Hazards from Common Causes in Engineering Di&C Systems Without Diverse Designs - State-of-the-Art ML23264A0252023-09-20020 September 2023 September 20, 2023 - Dent Presentation - John Mckirgan - Research Activities in Support of Digital Engineering in Nuclear Technology ML23262A9842023-09-19019 September 2023 MPA Seminar 2023 - Evaluation of Molten Salt Compatibility with Structural Alloys ML23256A0102023-09-18018 September 2023 State-of-the-art Approaches to Reduce the Potential for CCF in I&C Systems Conditions to Avoid the Need for Diversity in Design ML23251A0602023-09-13013 September 2023 Session 4 - Development of Standards for Artificial Intelligence Systems ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (Ripb) Standards ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23242A1182023-09-0707 September 2023 Research Challenges and Opportunities in the Safety Assurance of Nuclear Reactors ML23248A2142023-09-0606 September 2023 Reactor Safety: Regulatory Objectives & Framework ML23242A0032023-08-31031 August 2023 Reactor Protection System for the Virtual Ford Nuclear Reactor Designed-in Assurance ML23206A1592023-07-27027 July 2023 Identifying Hazards from Engineering Digital I&C Systems: State of the Art ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - 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Zorita Ril ML22143A8292022-05-25025 May 2022 11 - 2022-05 NRC-Industry Meeting - Raynaud - Favor Update ML22143A8362022-05-25025 May 2022 18 - 2022 NRC-Industry Mtls Exchange Mtg - NRC Xlpr Presentation ML22139A1372022-05-20020 May 2022 Presentation Slides for ACRS May 20, 2022 Meeting - ASME Sec XI Div. 2 ML22132A2992022-05-17017 May 2022 Staff Presentation for May 17, 2022 Public Meeting ML22102A1062022-04-0101 April 2022 ARPA-E Presentation-04-01-22-FINAL Research Activities in Nuclear Innovation and Regulation ML22060A0052022-03-0101 March 2022 Dt Public Meeting - NRC Slides ML21319A3902021-10-29029 October 2021 ASTM-E08-04 - Wrs Workshop - NRC Slides ML21230A3632021-08-18018 August 2021 Xlpr Maintenance ML21230A3662021-08-18018 August 2021 Xlpr Seminar_Applications_Code Case N-770 2024-01-16
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Text
xLPR Loss of Coolant Accident Frequency Estimates xLPR User Group Meeting August 18, 2021 1
Introduction The approach would be supported by the application of the Extremely Low Probability of Rupture (xLPR) leak-before-break (LBB) analysis tool, developed jointly by EPRI and the NRC Office of Nuclear Regulatory Research for Large Break- (LB) LOCAs. This tool could be used within this generic methodology to inform the probability of LB-LOCAs and that LB-LOCAs may be detected in sufficient time to allow for reactor shutdown before a reactor coolant system (RCS) piping rupture occurs. This approach facilitates the demonstration of no fuel rod burst (that is, no FFRD) and estimates the changes in CDF.
- From: Alternative Licensing Approaches for Higher Burnup Fuel: A Scoping Study on Deterministic and Risk-Informed Alternatives Supporting Fuel Discharge Burnup Extension. EPRI, Palo Alto, CA: 2020. 3002018457.
2
xLPR Work Scope
- Objective: Perform Probabilistic Fracture Mechanics (PFM) evaluation using xLPR to calculate the probabilities of Loss-of-Coolant-Accidents (LOCAs) as a function of line size
- Use xLPR to benchmark NUREG-1829, Vol. 1, Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process
- Validate (or replace) NUREG-1829 LOCA frequency estimates for use in high burnup fuel licensing
- Evaluate the time between detectable leakage and rupture to further inform the fuels licensing effort
- Approach: Project to be performed in phases
- Phase 1 consists of a PFM evaluation of two line sizes as a proof-of-concept and to develop methodology for possible expansion to other line sizes (detailed in this presentation)
- Phase 2 will expand the study to a variety of line sizes 3
Phase 1 Proof-of-Concept Study
- 1. Methodology for using xLPR to evaluate the probability of LOCAs as a function of line size
- 2. Estimation of the frequency of LOCA events
- 3. Statistics on time between detectable leakage and unstable pipe rupture
- Two lines for initial evaluations were selected considering:
- xLPR computational abilities
- NUREG-1829 LOCA frequency insights (smaller lines have higher freq. of rupture)
- Line size (mid-range of greatest interest to fuels licensing project)
- Input availability
- Degradation mechanisms (i.e., fatigue and primary water stress-corrosion cracking (PWSCC))
- Scope is limited to Pressurized-Water Reactors (PWRs)
- Base cases for each line include initial postulated flaws, fatigue and PWSCC crack growth (where applicable), and seismic occurrences
- Sensitivity cases were defined considering both inputs known to have influence on xLPR results and assumptions made during input development 4
Lines Selected for Evaluation
- Emphasis was placed on lines in the 6-10 in. (DN 150-250) range, as this range is of particular interest for fuel fragmentation, release, and dispersal (FFRD)
- Available input sources were reviewed to identify lines for which inputs to xLPR were readily available
- Licensee submittals in the NRCs Agencywide Documents Access and Management System
- EPRI reports
- xLPR documentation
- It was determined that of the two lines evaluated, one should be susceptible to PWSCC and the other only susceptible to fatigue since the population of dissimilar-metal welds is small Stainless Steel Weld Alloy 82/182 Weld
- Nominal pipe size (NPS) 6 (DN 150)
- NPS 12 (DN 300) SCH 140 or 160, resulting in ~10
- Represented by Westinghouse Safety
- High Pressure Safety Injection Injection
- Represented by Combustion Engineering Safety
- Population includes both hot leg and cold Injection/Accumulator leg temperature locations
- Cold leg temperature, unmitigated at most plants 5
Initial Results
- Runs are completed for the two lines selected for Phase 1 - EPRI Technical Update to be published in October 2021
- Phase 2 work extending the approach to additional lines will begin shortly -
EPRI report with results to be published in 2022
- As expected, LOCA frequencies are higher for lines susceptible to PWSCC
- When fatigue is the only active degradation mechanism, the number of cases with leakage/rupture is extremely low
- Results show rupture frequencies on similar order of magnitude or lower than NUREG-1829 LOCA frequencies
- Results are conservative as inservice inspection and leak rate detection were not credited
- It is noted that NUREG-1829 expert elicitation considered other degradation mechanisms in addition to those modeled in these xLPR analyses
- Time between leakage and rupture data analysis indicated notable margin for leak-before-break 6
Lessons Learned
- Performing sensitivity studies on key inputs as well as on inputs for which modeling decisions were made during input development adds confidence to the overall xLPR analysis results
- The xLPR analyses decoupled crack initiation and growth to work within xLPR memory limitations, significantly reducing the number of necessary realizations
- A methodology has been established that is able (with some refinements) to evaluate LOCA probabilities and time between detectable leakage and rupture for other PWR lines 7