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Category:Meeting Briefing Package/Handouts
MONTHYEARML24306A0122024-10-29029 October 2024 The Power Journey a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24299A1612024-10-25025 October 2024 Advanced Sensors and Instrumentation Characterizing Nuclear Cybersecurity Using Ai/Ml (Presentation) ML24292A0652024-10-18018 October 2024 Evolving the Legacy of DOE/EH-0545 in the DOE Handbook 1220 ML24292A0612024-10-18018 October 2024 The Power Journey - a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24284A1152024-10-11011 October 2024 S9 Panel ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24276A0012024-10-0202 October 2024 Regulatory Implications of Advanced Technologies for Component Condition Monitoring in Nuclear Energy Systems ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop ML24271A1332024-09-27027 September 2024 Xlpr - Looking to 20 Years of Continuous Development and Applications ML24254A2682024-09-16016 September 2024 Research Information Letter (Ril) 2024-12, Part II on 2023 NRC AMT Workshop ML24172A2962024-06-25025 June 2024 11 - NRC Support to Standards Orgs and Preparations for Future Reactors, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24172A2952024-06-25025 June 2024 10 - Overview of NRC Materials Research Supporting Long-Term Operation, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24162A2772024-06-10010 June 2024 Favpro Release Public Meeting Slides ML24137A0872024-05-14014 May 2024 Regulatory Considerations for Digital Twins for Nuclear Energy Systems - Presentation ML24115A0652024-04-23023 April 2024 Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation ML24075A1902024-03-31031 March 2024 Nondestructive Examination Research at NRC 3-8-24 RIL 2024-01, NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01)2024-03-31031 March 2024 NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01) ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24075A0272024-03-15015 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24016A1762024-01-16016 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 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 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 ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation ML23130A0042023-05-11011 May 2023 Challenges in Assuring Safety of Nuclear Reactor Protection Systems - One Perspective 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 2024-09-27
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24313A1662024-11-13013 November 2024 NRC Metals Research Supporting Long-Term Operation Update for Lwrs Stakeholders Meeting November 13, 2024 ML24306A0122024-10-29029 October 2024 The Power Journey a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24299A1612024-10-25025 October 2024 Advanced Sensors and Instrumentation Characterizing Nuclear Cybersecurity Using Ai/Ml (Presentation) ML24284A1152024-10-11011 October 2024 S9 Panel ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24276A0012024-10-0202 October 2024 Regulatory Implications of Advanced Technologies for Component Condition Monitoring in Nuclear Energy Systems ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24271A1332024-09-27027 September 2024 Xlpr - Looking to 20 Years of Continuous Development and Applications ML24254A2682024-09-16016 September 2024 Research Information Letter (Ril) 2024-12, Part II on 2023 NRC AMT Workshop ML24172A2962024-06-25025 June 2024 11 - NRC Support to Standards Orgs and Preparations for Future Reactors, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24172A2952024-06-25025 June 2024 10 - Overview of NRC Materials Research Supporting Long-Term Operation, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24162A2772024-06-10010 June 2024 Favpro Release Public Meeting Slides ML24137A0872024-05-14014 May 2024 Regulatory Considerations for Digital Twins for Nuclear Energy Systems - Presentation ML24115A0652024-04-23023 April 2024 Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation RIL 2024-01, NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01)2024-03-31031 March 2024 NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01) ML24075A1902024-03-31031 March 2024 Nondestructive Examination Research at NRC 3-8-24 ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24081A1102024-03-18018 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems - Final ML24075A0272024-03-15015 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24016A1762024-01-16016 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 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 ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (RIPB) Standards 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 ML23187A4862023-07-0606 July 2023 Nrc’S Digital I&C Research for Application in Nuclear Power Plants – Status Update Presentation at Npic&Hmit 2023 ML23187A4762023-07-0606 July 2023 Advanced Sensors and Instrumentation –Nrc Research Status Update Presentation at Npic&Hmit 2023 ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1772023-06-15015 June 2023 28 - NRC - Fatigue Data Sharing 2024-09-27
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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 oSpecifically 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.