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Category:Meeting Briefing Package/Handouts
MONTHYEARML24173A1852024-06-25025 June 2024 Industry/Nrc Materials Programs Technical Information Exchange - Advanced Manufacturing Technologies ML24173A1832024-06-21021 June 2024 12 - Subsequent License Renewal ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24051A0142024-02-21021 February 2024 NRC Meeting Presentation on SCC LIC-504 ML23268A3942023-09-21021 September 2023 NRC Activities in Advanced Manufacturing Technology ML23152A1722023-06-14014 June 2023 26 - NRC - Aging Related Inspection Procedures ML23152A1652023-06-14014 June 2023 10 - NRC - Operation Beyond 80 Years ML23152A1562023-06-14014 June 2023 09 - NRC - Status and Initiatives for SLR ML22311A0872022-11-28028 November 2022 From 40 to 60 to 80 Years – What Is Next for License Renewal in the USA? - Presentation Submitted to the IAEA Fifth International Conference on Nuclear Power Plant Life Management, November 28 to December 2, 2022 ML22266A2672022-09-28028 September 2022 Session 5 - Recent and Planned Developments and Updates in Codes and Standards Part 1 ML22166A3502022-06-14014 June 2022 Predicting Pipe Rupture Frequencies Using Xlpr ML22140A0212022-05-25025 May 2022 10 - Status of SLR in the United States 2022-05-25 ML22140A0232022-05-25025 May 2022 17 - RPV Embrittlement 2022-05-25 ML22143A6942022-05-25025 May 2022 01 - NRC - Welcome ML22143A8282022-05-25025 May 2022 08 - NRC - 5055a Ongoing Actions ML22143A8402022-05-25025 May 2022 22 - 2022 - Nvib - Mat Counterparts - ISI Thoughts ML22089A0372022-04-14014 April 2022 Can ISI Be Eliminated with Risk-Informed Decision Making ML22097A1302022-03-22022 March 2022 Reactor Vessel Embrittlement Presentation on March 22, 2022 ML21217A2632021-08-11011 August 2021 14 - NRC - Update on License Renewal for 40 Years and Research on 100 Years - August 11, 2021 ML21217A2622021-08-11011 August 2021 13 - NRC - Materials Exchange Public Meeting - HELB ML21217A2562021-08-10010 August 2021 07 - Imr Update August 2021 ML21217A2572021-08-10010 August 2021 08 - NRC - RPV Embrittlement Activity Update ML21217A2602021-08-10010 August 2021 11 - NRC - Ni-Alloy Crack Growth ML21217A3032021-08-10010 August 2021 04 - NRC - ISI-IST Update Interval ML21217A3042021-08-0909 August 2021 06 - NRC - Pfm Regulatory Guide Update - August 10-11, 2021 Industry/Nrc Materials Programs Technical Information Exchange ML21221A1242021-08-0909 August 2021 00 - NRC Reactor Materials Management ML21217A3022021-08-0909 August 2021 02B - NRC - Matl Tech Exchg - BWRVIP-100 ML21217A2592021-08-0909 August 2021 10A - PWROG MSC Overview August 2021 ML21174A3042021-06-23023 June 2021 SLRA RAI Response Public Meeting - 21-06-24 ML21042B8792021-02-18018 February 2021 Overview of Nuclear Power Plant License Renewal and Considerations for 40-Year Renewals ML20192A0022020-07-14014 July 2020 06 - RG 1.99 Revision Evaluation Effort for Industry / U.S. Nuclear Regulatory Commission Materials Programs Technical Information Exchange Public Meeting on July 14, 2020 ML20192A1372020-07-14014 July 2020 05A - 10 CFR 50.55a Rulemaking Plans Update for Industry / NRC Materials Programs Technical Information Exchange Public Meeting ML20155K8662020-06-0404 June 2020 June 4 Public Meeting Slides-rev1 (002) ML20155K8822020-06-0303 June 2020 NRC Public Meeting on 50_55a(b)(2)(xxvi) Condition - Final ML20125A0922020-05-0404 May 2020 May 4, 2020, Pre-submittal Meeting Handout Staff Comments Draft TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-06-25
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24173A1852024-06-25025 June 2024 Industry/Nrc Materials Programs Technical Information Exchange - Advanced Manufacturing Technologies ML24173A1832024-06-21021 June 2024 12 - Subsequent License Renewal ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24051A0142024-02-21021 February 2024 NRC Meeting Presentation on SCC LIC-504 ML23268A3942023-09-21021 September 2023 NRC Activities in Advanced Manufacturing Technology ML23152A1562023-06-14014 June 2023 09 - NRC - Status and Initiatives for SLR ML23152A1722023-06-14014 June 2023 26 - NRC - Aging Related Inspection Procedures ML23152A1652023-06-14014 June 2023 10 - NRC - Operation Beyond 80 Years ML23146A0972023-06-14014 June 2023 16 - NRC - French SCC Update ML23146A0882023-06-14014 June 2023 08 - NRC - ASME Rulemaking Update ML22311A0872022-11-28028 November 2022 From 40 to 60 to 80 Years – What Is Next for License Renewal in the USA? - Presentation Submitted to the IAEA Fifth International Conference on Nuclear Power Plant Life Management, November 28 to December 2, 2022 ML22307A0052022-11-28028 November 2022 How Did the United States Get to the Point of Renewing Nuclear Power Plant Operating Licenses to 80 Years? - Presentation Submitted to the IAEA Fifth International Conference on Nuclear Power Plant Life Management, November 28 to December 2 ML22166A3502022-06-14014 June 2022 Predicting Pipe Rupture Frequencies Using Xlpr ML22143A8402022-05-25025 May 2022 22 - 2022 - Nvib - Mat Counterparts - ISI Thoughts ML22140A0212022-05-25025 May 2022 10 - Status of SLR in the United States 2022-05-25 ML22140A0232022-05-25025 May 2022 17 - RPV Embrittlement 2022-05-25 ML22143A6942022-05-25025 May 2022 01 - NRC - Welcome ML22143A8272022-05-25025 May 2022 07- NRC Reactor Materials Management ML22143A8282022-05-25025 May 2022 08 - NRC - 5055a Ongoing Actions ML22089A0372022-04-14014 April 2022 Can ISI Be Eliminated with Risk-Informed Decision Making ML22097A1302022-03-22022 March 2022 Reactor Vessel Embrittlement Presentation on March 22, 2022 ML22033A0062022-03-10010 March 2022 RPV Embrittlement Poster 2-1-22 ML21217A2632021-08-11011 August 2021 14 - NRC - Update on License Renewal for 40 Years and Research on 100 Years - August 11, 2021 ML21217A2622021-08-11011 August 2021 13 - NRC - Materials Exchange Public Meeting - HELB ML21217A2562021-08-10010 August 2021 07 - Imr Update August 2021 ML21217A2572021-08-10010 August 2021 08 - NRC - RPV Embrittlement Activity Update ML21217A2602021-08-10010 August 2021 11 - NRC - Ni-Alloy Crack Growth ML21217A3032021-08-10010 August 2021 04 - NRC - ISI-IST Update Interval ML21217A3022021-08-0909 August 2021 02B - NRC - Matl Tech Exchg - BWRVIP-100 ML21221A1242021-08-0909 August 2021 00 - NRC Reactor Materials Management ML21217A3042021-08-0909 August 2021 06 - NRC - Pfm Regulatory Guide Update - August 10-11, 2021 Industry/Nrc Materials Programs Technical Information Exchange ML21217A2592021-08-0909 August 2021 10A - PWROG MSC Overview August 2021 ML21042B8792021-02-18018 February 2021 Overview of Nuclear Power Plant License Renewal and Considerations for 40-Year Renewals ML21015A3362021-01-15015 January 2021 00 - License Renewal Background and Status - 2021-01-15 ML20192A0022020-07-14014 July 2020 06 - RG 1.99 Revision Evaluation Effort for Industry / U.S. Nuclear Regulatory Commission Materials Programs Technical Information Exchange Public Meeting on July 14, 2020 ML20192A1372020-07-14014 July 2020 05A - 10 CFR 50.55a Rulemaking Plans Update for Industry / NRC Materials Programs Technical Information Exchange Public Meeting ML20192A0972020-07-14014 July 2020 04 - Probabilistic Fracture Mechanics Regulatory Guide for Industry / NRC Materials Programs Technical Information Exchange Public Meeting ML20176A2862020-06-25025 June 2020 June 25, 2020, Public Meeting Slides, Rev 1 ML20155K8662020-06-0404 June 2020 June 4 Public Meeting Slides-rev1 (002) ML20155K8822020-06-0303 June 2020 NRC Public Meeting on 50_55a(b)(2)(xxvi) Condition - Final ML20125A0922020-05-0404 May 2020 May 4, 2020, Pre-submittal Meeting Handout Staff Comments Draft TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-06-25
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Materials Programs Technical Information Exchange Public Meeting Update on High-Energy Line Break Activities Nuclear Regulatory Commission August 11, 2021 Virtual Meeting
Overview and Timeline June 2019: January 2021:
2015: Public Meeting New UNR that focuses User Need Request ML19214A095 on recommended option May 2019: Fall 2019 - Winter 2020: March 2021:
TLR - BTP 3-4 NRC staff developed Public Meeting Background and recommended option for ML21089A005 History alternative criteria ML19144A089
Revising BTP 3-4: Underlying Philosophy
- Significantly revamp existing BTP o Eliminate stress reduction criteria, relax CUF criterion o Consider other degradation mechanisms o Tailor fatigue evaluations, as needed, to applicable systems/components
- Support operating reactor, new reactor, and advanced reactor applications o Provide identical framework and approach o Require unique evaluations or analysis depending on reactor type
- Approach should be risk-informed o Consider both susceptibility to degradation and failure consequences o Utilize a graded approach consistent with the risk
- Broaden scope beyond classical, LWR welded-piping systems o Include other types of connections (e.g., bolted) o Include other appropriate passive components/systems
- The approach will be similarly applicable for high and moderate-energy level breaks
Guidance Approach: Similar Philosophy to SRP 3.6.3 - Leak-Before-Break (LBB)
Screening Analyses SRP 3.6.3 - LBB Determination Address consequences of Increasing Risk failure and susceptibility to Screening applicable degradation mechanisms Break Preclusion Demonstration Perform analyses to demonstrate that the Analyses probability of piping failure is extremely low Increasing Rigor
Current Status and Path Forward
- NRC staff is developing the framework and associated technical basis
o TLR on the technical basis for the alternative framework (mid 2022) o TLR that documents the alternative framework and associated technical basis (late 2022) o NUREG documenting the technical basis for the alternative framework (2023)