ML19025A307: Difference between revisions
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{{#Wiki_filter:& | {{#Wiki_filter: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 | |||
-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) | |||
-SECY-93-087: | 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* Outdated and not aligned with current DI&C technology | |||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 | |||
-informed and graded approach Develop a Digital I&C Policy that reflects a more risk | ©2018 Nuclear Energy Institute 6 | ||
-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 | |||
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 | ||
- | |||
©2018 Nuclear Energy Institute | 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 | ||
-14 to follow a graded and risk | ©2018 Nuclear Energy Institute 8 | ||
-informed approach that is flexible (i.e., not constrained to prescriptive adherence) | |||
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) | 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}} |
Latest revision as of 06:11, 20 October 2019
ML19025A307 | |
Person / Time | |
---|---|
Site: | Nuclear Energy Institute |
Issue date: | 01/28/2019 |
From: | Nuclear Energy Institute |
To: | Division of Licensing Projects |
Paige J, NRR/DLP, 415-1474 | |
Shared Package | |
ML19025A311 -Pkg. | List: |
References | |
Download: ML19025A307 (14) | |
Text
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