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Category:Meeting Briefing Package/Handouts
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 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 ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (Ripb) Standards ML23251A0602023-09-13013 September 2023 Session 4 - Development of Standards for Artificial Intelligence Systems 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 ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities ML23067A3402023-03-0707 March 2023 Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology ML22322A0432022-11-18018 November 2022 Regulatory Research on the Aging Management of Structures, Systems and Components in Nuclear Power Plants for Second License Renewal, Presentation Slides ML22280A1122022-10-0707 October 2022 Session 3 - Rapid Qualification of AMT Components - Is It Rocket Science? ML22266A2682022-09-28028 September 2022 Session 6 - Recent and Planned Developments and Updates in Codes and Standards Part 2 ML22266A2662022-09-28028 September 2022 Session 4 - Regulatory Initiatives for Streamlining Code & Standards Endorsement ML22174A3232022-06-27027 June 2022 NRC Presentation: Harvesting, an Overview and Historical Perspective 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 ML22143A8422022-05-25025 May 2022 27 - Zorita Ril 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 ML21230A3602021-08-18018 August 2021 NRC-EPRI Capstone Reports ML21230A3662021-08-18018 August 2021 Xlpr Seminar_Applications_Code Case N-770 ML21230A3642021-08-18018 August 2021 Xlpr Metamodeling ML21230A3632021-08-18018 August 2021 Xlpr Maintenance ML21230A3612021-08-18018 August 2021 Xlpr LOCA Frequencies Presentation for Xlpr User Group ML21230A3572021-08-18018 August 2021 LBB Studies V4 ML21230A3562021-08-18018 August 2021 International Pfm Code Benchmark ML21230A3582021-08-18018 August 2021 Lessons Learned - Xlpr Run Optimization ML21217A2602021-08-10010 August 2021 11 - NRC - Ni-Alloy Crack Growth ML21217A3042021-08-0909 August 2021 06 - NRC - Pfm Regulatory Guide Update - August 10-11, 2021 Industry/Nrc Materials Programs Technical Information Exchange ML21200A0722021-07-20020 July 2021 ACRS July 20 - Overview of ASME Section III Division 5 and NRC Review and Potential Endorsement.Pdf ML21173A1762021-06-22022 June 2021 Presentation to ACRS - Scheduled for June 25th 2021 in Pdf ML21011A2462021-03-0808 March 2021 RIC 2021 Digital Exhibit: Engagement with Codes & Standards Organizations 2024-01-16
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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 - Exploring International Collaboration ML23187A4762023-07-0606 July 2023 Advanced Sensors and Instrumentation NRC Research Status Update Presentation at Npic&Hmit 2023 ML23187A4862023-07-0606 July 2023 NRCs Digital I&C Research for Application in Nuclear Power Plants Status Update Presentation at Npic&Hmit 2023 ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23146A0952023-06-14014 June 2023 11 - NRC - Favpro ML23146A1022023-06-14014 June 2023 18 - NRC - Xlpr Update ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities ML23060A1432023-03-16016 March 2023 Lund - TH23 - v6 ML23067A3242023-03-0707 March 2023 Presentation - Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping with Thermal Fatigue Cracking ML23067A3402023-03-0707 March 2023 Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology ML23019A1502023-01-19019 January 2023 Public Q&A and Closing ML23019A1672023-01-19019 January 2023 Review of 06/14/2022 Meeting ML23019A1562023-01-19019 January 2023 NRC Use Cases for LOCA Frequency Estimates ML23019A1692023-01-19019 January 2023 Walk-In and Agenda for Meeting with the EPRI to Discuss Use of the Extremely Low Probability of Rupture Code for LOCA Frequency Estimates ML22321A0212022-12-0202 December 2022 Alloy 690/52/152 Thermal Aging: NRC Plans and Activities ML22322A0432022-11-18018 November 2022 Regulatory Research on the Aging Management of Structures, Systems and Components in Nuclear Power Plants for Second License Renewal, Presentation Slides ML22174A3232022-06-27027 June 2022 NRC Presentation: Harvesting, an Overview and Historical Perspective ML22143A8422022-05-25025 May 2022 27 - 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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ASSESSMENT OF SMALL DIAMETER DISSIMILAR-METAL WELD INSPECTION INTERVALS USING XLPR xLPR User Group Meeting August 18, 2021 1
Key Research Question
- With the updated Alloy 82/132/182 crack growth rates Excerpt from ASME Code Case N-770-6, Table 1 in EPRI report MRP-420, Rev. 1, is a change in the reinspection Item Parts Inspection Requirement interval warranted for PWR cold Unmitigated butt weld at leg dissimilar metal (DM) butt Cold Leg operating Visual exam once per interval welds from those that are B-1 temperature 274°C (525°F) and < 304°C Volumetric exam every currently established in ASME (580°F), less than NPS 14 second inspection period Code Case N-770? (DN 350) not to exceed 7 years Unmitigated butt weld at Visual exam once per
- Code Case N-770 was Cold Leg operating temperature 274°C interval developed using crack growth B-2 (525°F) and < 304°C Volumetric exam once per rates of Alloy 82/182 from (580°F), NPS 14 (DN 350) or interval MRP-115 larger 2
Methodology
- Individual steps performed are as follows:
- 1. Cold leg DM butt welds and the various configurations from each Nuclear Steam Supply System (NSSS) plant type were reviewed and grouped by size
- 2. Additional input data were collected, including welding residual stresses, material properties, environmental conditions, and inspection detection capabilities
- 3. Probabilistic fracture mechanics (PFM) evaluations were performed using the recently released xLPR (Extremely Low Probability of Rupture) software
- 4. Deterministic fracture mechanics (DFM) evaluations were performed using average parameters to provide verification of the PFM analysis results 3
Component Grouping
- A compilation of all the cold leg temperature DM butt weld components Westinghouse was developed for the U.S. operating
- Auxiliary Head Adapter Nozzle - Small pressurized water reactor (PWR) fleet Diameter
- NSSS designs from Westinghouse, Combustion Engineering, and Babcock & Combustion Engineering Wilcox were considered
- Charging Nozzle - Small Diameter
- All welds less than reactor coolant loop
- Spray Nozzle - Small Diameter (RCL) size were grouped as either medium
- Letdown/Drain Nozzle - Small Diameter or small
- Safety Injection Nozzle - Medium
- Medium > nominal pipe size (NPS) 8 (DN200) Diameter
- The small size was further divided based on Babcock & Wilcox wall thickness
- High Pressure Injection Nozzle - Small
- Bounding geometry and stresses were Diameter determined for each grouping
- Letdown/Drain Nozzle - Small Diameter
- Core Flood Nozzle - Medium Diameter 4
PFM Methodology
- The PFM evaluations were performed using the xLPR software
- Probabilistic analysis considers three inservice inspection (ISI) scenarios
- Current 7-year interval using Code Case N-770 inspection criteria based on MRP-115 (baseline) and MRP-420, Rev. 1 crack growth rates
- Investigating 10-year interval with MRP-420 crack growth rates
- Also included mixed ISI cases representing two ISI intervals of 7 years followed by 10-year intervals Inspection Scenarios (at Years)
ISI 1 ISI 2 ISI 3 7, 14, 21, 28, 35, 42, 49 10, 20, 30, 40, 50 7, 14, 24, 34, 44 (every 7 years) (every 10 years) (two 7 years + every 10 years) 5
PFM Methodology (contd)
- Operating temperatures, water chemistry, and operating loads were collected for operating plants
- A pre-existing, single, primary water stress-corrosion cracking (PWSCC) flaw in the DM butt weld was assumed with no additional initiation during the evaluation period
- Consistent with the MRP-139 and ASME Code Case N-770 bases
- Welding residual stresses included the effects of inside diameter weld repairs
- The material properties required for flaw stability are obtained from the material library of xLPR V2.1
- The probability of detection curves from MRP-262, Rev. 3 were used 6
PFM Methodology (contd)
- From the PFM evaluations, probabilities of leak and rupture were calculated
- The acceptance criterion adopted for this study: increase in failure probability per year must be less than 1x10-6
- Consistent with U.S. NRC Regulatory Guide 1.174 as discussed in the development of the proposed xLPR leak-before-break acceptance criteria 7
PFM Results
- In total, 24 base cases were evaluated to compare the change in failure probability due to relaxing the inspection interval
- An additional 5 sensitivity studies were also evaluated
- For the Medium DM butt weld, the changes in leak and rupture probabilities were either zero or negative, which indicates that the proposed 10-year inspection interval satisfies the acceptance criteria
- For Small DM butt welds, the changes in leak and rupture probabilities demonstrated that the proposed 10-year inspection interval is acceptable if two 7-year inspections have been previously performed 8
Conclusions
- The evaluation demonstrated that the failure probability increase for small and medium diameter DM butt welds was within the acceptance criteria when comparing the current requirements (7 years) and the proposed alternative inspection frequency (10 years)
- For Small DM butt welds the conclusion is conditional on two 7-year inspections have been previously performed
- The work included bounding values that are intended to be generally representative of the fleet based on various configurations; however, the following areas need to be addressed to demonstrate plant-specific applicability
- Geometry and stress
- Welding residual stresses
- Environmental conditions (temperature and hydrogen addition)
- Also see PVP2021-62560 for a summary 9