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Category:Meeting Briefing Package/Handouts
MONTHYEARML24302A0912024-10-0505 October 2024 Welcome Slides ML24274A3232024-10-0404 October 2024 S9P6-Kojima Concrete Harvesting Activities Plans and Related Priority Research Topics in Japan R2 ML24257A0902024-09-17017 September 2024 05 Osvaldo Pensado Swri September 2024 NRC Ai Public Workshop 09/17/2024 ML24263A2552024-09-17017 September 2024 02 Doug Eskins NRC September 2024 NRC Ai Public Workshop 09-17-2024 ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0182024-07-23023 July 2024 3-Base: Isolation/Observations - Final Stakeholder Meeting, 07-24-24 ML24172A3022024-06-25025 June 2024 Extremely Low Probability of Rupture (Xlpr) Code, NRC Perspectives and Activities ML24045A2332024-03-12012 March 2024 RIC 2024 W11 - Human in the Loop: the Changing Role of Humans in New Advanced Reactor Designs - D. Desaulniers Presentation ML24005A1022024-01-0505 January 2024 RES - High Burnup Fuel Source Term Accident Analysis Briefing - Workshop Jan 09, 2024 ML23214A0342023-08-0202 August 2023 RIC 2023 Regulatory Information Conference (RIC) Project Advanced Characterization of ATF Cladding for Understanding Their Degradation Under Short-time Temperature Excursions and Implications in Dry Storage ML23200A3442023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Joseph Staudenmeier on Models for Thermal Hydraulic Safety Analysis ML23045A2852023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) Advancing the Infrastructure for Using PRA in Decision-Making Technical Session T5 ML22340A5892022-12-13013 December 2022 Boas HPS_Drop-in_12-13-2022 ML22297A0322022-10-31031 October 2022 Nuclear Data at the Us NRC ML22235A6512022-09-0101 September 2022 FY22-24 NRC Research Prospectus Final for Review ML22220A0762022-08-0808 August 2022 Advanced Reactor Research Activities in Nuclear Innovation ML22221A2422022-07-30030 July 2022 KM Session Ai Strategic Plan Overview 20223006 ML22203A0852022-07-27027 July 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22174A3242022-06-27027 June 2022 NRC Presentation: NRC Harvesting Strategy, Coordination, and Activities ML22178A1792022-06-27027 June 2022 Harvesting - an Overview and Historical Perspective, June 27, 2022 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 NUREG-1829, Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results2022-06-14014 June 2022 Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results ML22166A3492022-06-14014 June 2022 Passive System LOCA Frequency Estimation and Break Size Selection ML22143A9262022-05-26026 May 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22131A3362022-05-13013 May 2022 DG-1402 April 13 2022 Public Meeting Slides ML22136A1102022-05-11011 May 2022 Presentation 1 - NRC Opening Remarks by T. Aird and C. Barr ML22102A0002022-04-0505 April 2022 Us NRC and Research Centre Rez (Czech Rep.) 2nd Bilateral Meeting, 04/05/2022 - NRC Presentation ML22083A0302022-03-24024 March 2022 March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel ML22040A1382022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Franovichm - Safety Improvements Using Risk Insights ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview ML21228A0812021-08-16016 August 2021 Agenda Dtaant Workshop Sept 2021 ML21221A1912021-08-11011 August 2021 Presentation on Regulatory Guide 1.9 Revision 5 for NRC Public Meeting with NEI on August 11 2021 ML21217A2612021-08-0909 August 2021 12A - NRC - Xlpr Slides for Mtls Exchange ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21183A2012021-07-0707 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21183A2022021-07-0606 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21113A0822021-05-0606 May 2021 Appendix B - Workshop Slides ML21098A1292021-04-0606 April 2021 1E - Sierra Modeling ML21098A1312021-04-0606 April 2021 1G - Fragility ML21098A1282021-04-0606 April 2021 1D - Modeling Overview ML21098A1262021-04-0606 April 2021 1B - Overview ML21069A0202021-03-0303 March 2021 Phenomena Identification and Ranking Tables: U.S. NRC Perspective ML21057A1672021-03-0101 March 2021 Public Meeting - HELB - NRC Presentations on Alternative Acceptance Criteria for Postulating Pipe Break Locations - March 2021 ML20336A0042020-12-0707 December 2020 Opening Session - NRC Public Workshop on Advanced Manufacturing Technologies for Nuclear Applications ML20304A5012020-11-0505 November 2020 Rev 3 - ACRS Fc Briefing for the Advisory Committee on Reactor Safeguards Full Committee - Final ML20283A6162020-10-15015 October 2020 Presentation: Nrc'S Preparations for Advanced Reactor Licensing, ORNL Molten Salt Workshop, October 14-15, 2020 ML20289A6582020-10-0808 October 2020 Enclosure 3 - NRC Presentation on Nrc'S Crediting FLEX Effort 2024-09-17
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MONTHYEARML24302A0912024-10-0505 October 2024 Welcome Slides ML24274A3232024-10-0404 October 2024 S9P6-Kojima Concrete Harvesting Activities Plans and Related Priority Research Topics in Japan R2 ML24263A2552024-09-17017 September 2024 02 Doug Eskins NRC September 2024 NRC Ai Public Workshop 09-17-2024 ML24257A0902024-09-17017 September 2024 05 Osvaldo Pensado Swri September 2024 NRC Ai Public Workshop 09/17/2024 ML24213A0642024-07-31031 July 2024 Presentation - NRC Work on Thermal Aging Embrittlement of Austenitic Stainless Steel Weld Metal Implications for Section XI Flaw Evaluation Procedures ML24205A0182024-07-23023 July 2024 3-Base: Isolation/Observations - Final Stakeholder Meeting, 07-24-24 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24172A3022024-06-25025 June 2024 Extremely Low Probability of Rupture (Xlpr) Code, NRC Perspectives and Activities ML24029A2372024-03-12012 March 2024 03/12-14/2024 Regulatory Information Conference (RIC) ML24045A2332024-03-12012 March 2024 RIC 2024 W11 - Human in the Loop: the Changing Role of Humans in New Advanced Reactor Designs - D. Desaulniers Presentation ML24005A1022024-01-0505 January 2024 RES - High Burnup Fuel Source Term Accident Analysis Briefing - Workshop Jan 09, 2024 ML23214A0342023-08-0202 August 2023 RIC 2023 Regulatory Information Conference (RIC) Project Advanced Characterization of ATF Cladding for Understanding Their Degradation Under Short-time Temperature Excursions and Implications in Dry Storage ML23200A3442023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Joseph Staudenmeier on Models for Thermal Hydraulic Safety Analysis ML23166A1122023-06-14014 June 2023 Presentation on Artificial Intelligence and Machine Learning Support for Probabilistic Fracture Mechanics Analysis ML23193B0422023-06-11011 June 2023 Applications of the Extremely Low Probability of Rupture (Xlpr) Code ML23150A0242023-05-17017 May 2023 0a -Welcome (NRC) ML23150A0262023-05-17017 May 2023 0c - Working Group ML23121A2552023-05-0202 May 2023 Public Meeting to Discuss Revision of Regulatory Guide 1.200 and Updates to Technical Guidance Related to Risk-Informed Activities ML23045A2852023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) Advancing the Infrastructure for Using PRA in Decision-Making Technical Session T5 ML23058A2132023-02-27027 February 2023 HTGR Workshop 2023 Slides - Final ML22297A0322022-10-31031 October 2022 Nuclear Data at the Us NRC ML22235A6512022-09-0101 September 2022 FY22-24 NRC Research Prospectus Final for Review ML22220A0762022-08-0808 August 2022 Advanced Reactor Research Activities in Nuclear Innovation ML22221A2422022-07-30030 July 2022 KM Session Ai Strategic Plan Overview 20223006 ML22203A0852022-07-27027 July 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22179A3342022-06-28028 June 2022 NRC Public Meeting - Advanced Manufacturing Technologies, June 28, 2022 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 ML22178A1792022-06-27027 June 2022 Harvesting - an Overview and Historical Perspective, June 27, 2022 ML22174A3242022-06-27027 June 2022 NRC Presentation: NRC Harvesting Strategy, Coordination, and Activities ML22166A3492022-06-14014 June 2022 Passive System LOCA Frequency Estimation and Break Size Selection NUREG-1829, Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results2022-06-14014 June 2022 Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results ML22143A9262022-05-26026 May 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22131A3362022-05-13013 May 2022 DG-1402 April 13 2022 Public Meeting Slides ML22136A1102022-05-11011 May 2022 Presentation 1 - NRC Opening Remarks by T. Aird and C. Barr ML22102A0002022-04-0505 April 2022 Us NRC and Research Centre Rez (Czech Rep.) 2nd Bilateral Meeting, 04/05/2022 - NRC Presentation ML22083A0302022-03-24024 March 2022 March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel ML22080A0472022-03-22022 March 2022 Anticipated Impacts of Nuclear Accidents, Presentation for 2022 Society for Benefit-Cost Analysis Annual Conference, 3-22-2022 ML22083A2042022-03-15015 March 2022 Presentation on NRC Regulatory Research - Enabling Regulatory Readiness for Accident Tolerant Fuel, March 22, 2022 ML22140A3092022-03-0808 March 2022 bush-goddards-hv-w12 ML22140A3112022-03-0808 March 2022 coffins-hv-t7 ML22040A1382022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Franovichm - Safety Improvements Using Risk Insights ML22040A1802022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Thaggard M - Safety Marker Study ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview ML21228A0812021-08-16016 August 2021 Agenda Dtaant Workshop Sept 2021 ML21221A1912021-08-11011 August 2021 Presentation on Regulatory Guide 1.9 Revision 5 for NRC Public Meeting with NEI on August 11 2021 ML21217A2612021-08-0909 August 2021 12A - NRC - Xlpr Slides for Mtls Exchange ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit 2024-09-17
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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 July 7, 2021
Agenda
- 1. Introduction
- 2. Existing Guidance
- 3. Significant Changes
- 4. Proposed New Guidance
- 5. Public Comments and Resolutions
- 6. Questions and Comments Slide 2
Introduction Current NRC guidance in Regulatory Guide 1.9 has not been updated since 2007. It does not reflect all the possible types of alternative onsite emergency AC power sources.
The NRC is issuing Revision 5 of Regulatory Guide 1.9:
- Endorse new and updated IEEE standards
- Introduce technology-neutral guidance other than diesels, to include combustion turbine generators (CTGs) and other types of the emergency power sources for the onsite alternative alternating current (AC) electric power system.
Purpose of introducing technology-neutral provisions:
- Acknowledge that future applications may use alternative onsite emergency power supplies for advanced reactors and nuclear facilities.
- Provide an initial path in the regulatory review process for alternative power supplies.
- Establish a foundation for alternative power supplies by describing acceptance criteria.
Slide 3
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 facilities.
Slide 4
Significant Changes This revision (Rev 5) endorses one new and updates another IEEE standard 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 IEEE Standard 387-2017 was updated from 1995 version o Includes specific details on design and testing considerations Slide 5
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 Industry developed this new standard in 2019 based upon Interim Staff Guidance (DC/COL-ISG-021) o Specifically includes additional guidance on CTGs principal design criteria, design features, qualification considerations, and testing requirements.
Slide 6
Proposed New Guidance Includes provisions for alternatives for onsite standby emergency AC 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.).
- References applicable guidance provided in Regulatory Guides:
1.75, 1.6, 1.81, 1.118, 1.89, 1.100, 1.164, 1.28, 1.155 and 1.189 Includes additional design and testing considerations for EDGs, CTGs, and other emergency AC power sources.
Slide 7
Proposed New Guidance (Cont.)
This Revision introduces a new technology-neutral concept for power sources other than EDGs and CTGs.
Since the range of possible alternative power sources is very wide in scope, the staff provided only basic foundations identifying the regulatory requirements for an alternative onsite power sources.
Revision 5 is only introducing guidelines for alternative power sources. The staff is open to reviewing and endorsing future industry standards for alternate onsite power sources.
Slide 8
Proposed New Guidance (cont.)
Sample Supplements and Clarifications to IEEE 387-2017:
Design and Application Considerations for testability and synchronization capabilities was supplemented:
- to address testing of the EDG operating in parallel with the preferred power source in the event the preferred power source has transients.
Design and Testing Considerations was clarified:
- The design should allow testing of the EDGs to envelop the parameters of operation.
Operations 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.
Slide 9
Proposed New Guidance (cont.)
Sample Supplements and Clarifications to IEEE 2420-2019:
- Design and Application Considerations for testability and synchronization capabilities was supplemented:
- to address testing of the CTG operating in parallel with the preferred power source in the event the preferred power source has transients.
- Design and Testing Considerations was clarified:
- The exhaust system should be purged before startup or during shutdown
- The pressure loss associated with the air intakes may be significant. Design should consider the local environment and the possibility of condensation of moisture from the ambient humidity
- Recommended Parameters was clarified:
- adding additional items to be monitored to indicate the need for an overhaul.
Slide 10
Proposed New Guidance (cont.)
- 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.
Slide 11
Public Comments and Resolution Summary:
- 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.
Slide 12
Public Comments and Resolution(cont.)
Comments of interest from NEI (Comments No. 1, 2, 3, and 5)
o 30-day timeframe removed. Mission time now refers to licensing bases.
- A requirement for constructing a chamber for testing various atmospheric conditions would be impractical.
o Clarified language to state the design of EDG encompasses a temperature and humidity band of operation.
- The design requirement associated with preferred offsite power should be considered part of the remote protection system per IEEE Standard 387, hence, not within the scope of this regulatory guide.
o EDG has adequate internal protection to sustain its mission while paralleled to grid.
Slide 13
Public Comments and Resolution(cont.)
Comments of interest from IEEE
- Almost identical to NEI comments. They were addressed within the responses to NEI comments accordingly.
Comments from Members of Public
- Clarification on the use of terms accident
- Terminology used was consistent with the terminology in the endorsed version of IEEE Std 387-2017.
- Clarification for bypassing non-critical trips of EDG.
- Bypassing of noncritical trips during accidents is expected and it is important to take measures to ensure that spurious actuation of these other protective trips does not prevent the EDGs from performing their function during accident mode of operation.
The endorsement of these IEEE standards does not add any new regulatory positions regarding design basis events (DBE), anticipated operational occurrences (AOOs), loss of offsite power (LOOP) with accident conditions.
Slide 14
Steps Towards Issuance
- Briefed ACRS subcommittee and received feedback.
- Brief ACRS full committee.
- Issuance of new guide is expected in July.
Slide 15
Questions and Comments
?
Slide 16