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Category:Slides and Viewgraphs
MONTHYEARML24310A2262024-11-0606 November 2024 NEI Preliminary Perspectives on NRC Draft Noak Microreactor White Paper ML24303A2212024-10-29029 October 2024 NEI SDP Realism Presentation for October 30, 2024 Public Meeting ML24291A0062024-10-17017 October 2024 NEI Slide Presentation: ACRS Regulatory Policies and Practices - Draft White Paper on Nth-of-a-Kind (Noak) Micro-Reactor Licensing and Deployment Considerations - Sc - October 17, 2024 ML24267A0032024-09-25025 September 2024 NEI Slides for ROP Public Meeting Sept 2024 ML24263A2592024-09-17017 September 2024 06 Jim Slider NEI September 2024 NRC Ai Public Workshop 09-17-2024 ML24249A2012024-09-0909 September 2024 NEI Presentation - Sept 9 Public Meeting - Flooding DGs - Final ML24249A1152024-09-0505 September 2024 Power Uprate September 5, 2024 Public Meeting Slides ML24243A1612024-08-30030 August 2024 Slide Presentations for High Burnup (Hbu) Workshop V ML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - 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NRC - Workshop3 - Non-LOCA Release Fractions Feedback - Final ML24067A0072024-03-0808 March 2024 2 - NRC - Workshop3 - Non-LOCA - FFRD - Final ML24067A0092024-03-0808 March 2024 3 - NRC - Worshop3 - CR Dose Presentation - Final ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24043A1162024-02-13013 February 2024 3- EQ Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24010A0202024-01-11011 January 2024 Public Meeting on SLR Efficiencies - NEI Presentation ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23261C3792023-09-27027 September 2023 NEI 22-04 Pre-Submittal Meeting with NRC - September 27, 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23242A1662023-08-30030 August 2023 The Future of Nuclear Power: 2023 Baseline Survey (Slides) ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23228A0042023-08-18018 August 2023 NEI Slides for Public Meeting to Discuss Possible Efficiencies on the Subsequent License Renewal Review - August 18, 2023 ML23191A0162023-07-11011 July 2023 NEI Comments on Risk-Informed Process for Evaluation (RIPE) DORL TSG - 7/11/23 Public Meeting Slides from NEI 2024-09-09
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Digital I&C Strategy NEI DI&C Working Group January 31, 2019 NRC Public Meeting
©2018 Nuclear Energy Institute
Overarching Principles Incorporate defined boundaries Apply risk-informed insights Leverage robust design processes Capitalize on international operational experience and standards
©2018 Nuclear Energy Institute 2
Discussion topics Identify desired outcomes Identify barriers to progress Propose solutions to overcome barriers Summary
©2018 Nuclear Energy Institute 3
What does the end look like?
Utilities successfully design, develop, implement, and license digital upgrades to protection and control systems to support plant modernization and improve plant safety and reliability
©2018 Nuclear Energy Institute 4
Barrier #1 - Common Cause Failure (CCF)
BTP 7-19 guidance has evolved over the years and expanded the scope of the SRM-SECY-93-087 policy Concerns with SRM-SECY-93-087:
- Deterministic solutions to mitigate the potential for CCF
- Outdated and not aligned with current DI&C technology
©2018 Nuclear Energy Institute 5
Solution #1 - CCF Revise BTP 7-19 to be consistent with the concepts and scope of CCF treatment as described in Revision 4, a more risk-informed and graded approach Develop a Digital I&C Policy that reflects a more risk-informed and graded approach to safety Employ concepts from the EPRI Digital Engineering Guide, which leverages principles from International Electrotechnical Commission (IEC) Standards
©2018 Nuclear Energy Institute 6
Solution #1 - Potential Solutions to CCF Safety Related Safety Related Non-Safety Related (Protection) (Non-Protection)
Standardized Digital Design Standardized Digital Design Standardized Digital Design Short Term Process Process Process Industry EPRI Technical Guidance EPRI Technical Guidance EPRI Technical Guidance Guidance RIS 2002-22 Supp. 1 RIS 2002-22 Supp. 1 Short Term NRC Review BTP 7-19, Revision 4 Concepts RIS 2002-22 Supp. 1 No Changes Needed Guidance Standardized Digital Design Standardized Digital Design Standardized Digital Design Long Term Process Process Process Industry NEI YY-XX link to EPRI Technical NEI YY-XX link to EPRI Technical NEI YY-XX link to EPRI Technical Guidance Guidance Guidance Guidance Long Term Approval of NEI YY-XX Content of RIS 2002-22, Supp. 1 NRC Review No Changes Needed Develop DI&C Commission Policy Captured as Durable Guidance Guidance
©2018 Nuclear Energy Institute 7
Barrier #2 - Software Development Standards and Guidance Software development standards for safety-related SSCs are not commensurate with safety and not aligned with current technology BTP 7-14 Guidance does not follow a graded and risk-informed approach
©2018 Nuclear Energy Institute 8
Solution #2 - Software Development Standards and Guidance Consider guidance from international standards associated with safety-related software development Revise BTP 7-14 to follow a graded and risk-informed approach that is flexible (i.e., not constrained to prescriptive adherence)
Leverage digital I&C operating experience from the international nuclear community (e.g., Électricité de France)
©2018 Nuclear Energy Institute 9
Barrier #3 - I&C System Architecture Development Chapter 7 of the Standard Review Plan (SRP) has fragmented and incomplete review guidance for I&C system architectures
©2018 Nuclear Energy Institute 10
Solution #3 - I&C System Architecture Development Consider international guidance related to the design and development of I&C system architectures Employ concepts from the EPRI Digital Engineering Guide (DEG)
©2018 Nuclear Energy Institute 11
Barrier #4 - Limited Functionality I&C Devices Insufficient guidance on limited functionality I&C devices
©2018 Nuclear Energy Institute 12
Solution #4 - Limited Functionality I&C Devices Consider international guidance associated with limited functionality I&C devices
©2018 Nuclear Energy Institute 13
Summary Strategy is outcome oriented Proposed solutions overcome barriers Leverage international successes in DI&C Alignment with NRC initiatives and principles
©2018 Nuclear Energy Institute 14