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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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Revision 5 to Regulatory Guide 1.9, Application and Testing of Onsite Emergency Alternating Current Power Sources in Nuclear Power Plants NRC Staff Presentation to the Advisory Committee on Reactor Safety June 25, 2021
Agenda
- 1. Introduction
- 2. Existing Guidance
- 3. Significant Changes
- 4. Proposed New Guidance
- 5. Conclusion
Introduction Current NRC guidance in Regulatory Guide 1.9 has not been updated since 2007. It does not reflect all the possible types of different onsite emergency power sources that are available today.
The NRC is issuing Revision 5 of Regulatory Guide 1.9 as technology-neutral to include diesels, combustion turbine generators (CTGs), and other types of the emergency power sources for the onsite alternative alternating current (AC) electric power system.
Technology-neutral benefits:
- Facilitate application processes allowing use of alternative onsite emergency power supplies in the future for advanced reactors and nuclear facilities.
- Reduce the number of regulatory guides that will be required to cover other alternatives.
- Reduce the overall regulatory review process.
Existing NRC Guidance Regulatory Guide 1.9, Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants was last updated in 2007 to Revision 4.
Regulatory Guide 1.9 provides guidance that the NRC staff considers as an acceptable method for satisfying NRC regulations (mainly GDC 17 and 18) with respect to the design, qualification, and testing of emergency power sources used in onsite AC electric power systems for nuclear power plants.
Significant Changes This revision (Rev 5) endorses the following two IEEE standards in full, with supplements and clarifications:
- IEEE Standard 387-2017, IEEE Standard for Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations o Includes specific details based on lessons learned from comprehensive reviews of operating reactors, new reactor applications, and other nuclear facilities.
Significant Changes (cont.)
- IEEE Standard 2420-2019, IEEE Standard Criteria for Combustion Turbine-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations o Specifically includes additional guidance on CTGs principal design criteria, design features, qualification considerations, and testing requirements, based on the reviews performed for the US-Advanced Pressurized-Water Reactor and other Interim Staff Guidance.
Significant Changes (cont.)
Clarifications:
- Design and Application Considerations in 387-2017 for testability and synchronization capabilities was supplemented:
- to address testing EDGs in the event the offsite power source has transients resulting in voltage and frequency perturbations.
- Design and Testing Considerations in 387-2017 was clarified:
- to include how the EDGs envelop parameters of operation.
- Operations in 387-2017 was clarified:
- to include that licensees should monitor EDGs cumulative operating time above the nominal rating for additional restrictions as specified in manufacturer-recommended accelerated maintenance requirements and industry consensus group recommendations.
Significant Changes (cont.)
Supplements:
- Both IEEE standards were supplemented to include verification of all subsystems such as fuel oil, lube oil, cooling, starting, and piping systems credited for operation.
Other important changes:
- Removal of testing and design requirements from Rev 4 because they have been incorporated in the updated IEEE 387-2017.
- Title of Regulatory Guide 1.9 changed to be more technology neutral, Application and Testing of Onsite Emergency Alternating Current Power Sources in Nuclear Power Plants.
Proposed New Guidance
- Includes provisions for alternatives for onsite standby emergency power supplies that meet the intent of 10 CFR 50 and 10 CFR Part 52 requirements in consideration for small modular reactors, advanced reactors, and other nuclear facilities.
- Includes criteria derived from General Design Criteria (GDC) 17 and GDC 18 (e.g., information on capacity, capability, independence, redundancy, testability, inspection, qualification, etc.).
- Includes additional design and testing considerations for EDGs, CTGs, and other emergency AC power sources.
Public Comments
- Received 51 comments from NEI, IEEE, and members of public.
- One significant change made to the background section was to combine the two sections on EDGs and CTGs into one.
- The rest of the comments were minor and incorporated by editorial changes.
- Several other comments did not require changes because they were determined to be beyond the scope of this regulatory guide.
Steps Towards Issuance
- Brief ACRS on changes and receive feedback.
- Issuance of new guide is expected in late June or early July.
Conclusion
- The staff expects publication of Revision 5 of Regulatory Guide 1.9 endorsing existing two industry standards within the next month.
- Revision 5 removes details of design and testing considerations of EDGs because these details were included in IEEE 387-2017.
- Revision 5 includes provisions for alternative emergency power sources (technology-neutral) for supplying onsite AC electric power systems.