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Category:Meeting Briefing Package/Handouts
MONTHYEARML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 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 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 ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23115A0302023-04-27027 April 2023 NEI Perspective on Performance Monitoring in Use of Probabilistic Fracture Mechanics for Optimizing Inspections of Non-RPV Pressure Vessels, April 27, 2023 ML23088A0822023-03-30030 March 2023 NEI Presentation - March 30, 2023 PRA Configuration Control Public Meeting ML23082A0572023-03-28028 March 2023 Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk ML23079A2642023-03-23023 March 2023 General Visual Examination of Containment Surfaces Covered by Insulation - March 23, 2023 Public Meeting Slides from NEI ML23210A0042023-03-15015 March 2023 Destination: Termination, NRC Regulatory Information Conference ML23045A2892023-03-14014 March 2023 RIC 2023 - 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric).Operational and Safety Benefits of Risk Informed Applications ML23061A0292023-03-0202 March 2023 NEI Presentation - Advanced Reactor Digital I&C Licensing Workshop 1 ML23013A0782023-01-13013 January 2023 PI&R Inspection Discussion for January 2023 ROP Public Meeting ML23041A4342022-12-15015 December 2022 NEI Presentation for December 15, 2022 Industry Spent Fuel Activities Prioritization Meeting ML22291A4442022-10-11011 October 2022 NEI 22-01 License Termination Plan Process Presentation at October 11 2022 Meeting on NUREG-1757 Vol. 2 ML22266A2632022-09-28028 September 2022 Session 2 - Advanced Reactor Developers Perspectives on Codes and Standards ML22250A7122022-09-21021 September 2022 NEI 22-03 Presentation Slides for NRC Public Meeting (Sept. 21, 2022) ML22235A7032022-08-24024 August 2022 NEI Presentation for Aug 26, 2022 Public Meeting - Source Terms and Radiological Consequence Analyses ML22194A0682022-07-18018 July 2022 NEI Presentation for NEI 22-02 Rsi Response ML22174A2822022-06-22022 June 2022 NEI Presentation for Public Meeting with NMMSS Users Community to Discuss Foreign Obligation Reporting Requirements for Low Enriched Uranium ML22172A1352022-06-21021 June 2022 NEI Presentation for Public Meeting Industry Perspectives on Rulemaking for Greater than 5 Percent Enrichment ML22143A8542022-05-20020 May 2022 Nuclear Energy Institue (NEI) Presentation Slides to ACRS Subcommittee on CCF Secy Paper, May 20, 2022 ML22136A1162022-05-11011 May 2022 Presentation 5 - Utilizing the Nuclear Energy Institute (NEI) 07-07 Industry Groundwater Protection Initiative as a Foundation for Addressing Subsurface Site Assessments ML22088A0342022-03-29029 March 2022 Public Meeting Presentation by NEI Regarding Part 53 Rulemaking: Selected Topics ML22077A4012022-03-23023 March 2022 NEI INL Presentation March 23, 2022, NRC Workshop Isv Hfe Issue ML22070B1212022-03-16016 March 2022 Industry Perspective on IEEE Std -1819 ML22140A3612022-03-10010 March 2022 mccullumr- hv-th29 ML22060A0022022-03-0101 March 2022 Dt Public Meeting - NEI Slides ML22042A0092022-02-11011 February 2022 NEI Presentation Slides for February 15, 2022, Public Meeting on Common-Cause-Failure (CCF) Policy ML22031A2612022-01-31031 January 2022 NEI Feb 2022 PRA Configuration Control Inspection Workshop ML22027A3922022-01-27027 January 2022 NEI 50.59 Risk Insights Presentation ML21350A2122021-12-17017 December 2021 Slide Presentation: ACRS Future Plant Designs Subcommittee Meeting, 10 CFR Part 53, Licensing and Regulation of Advanced Nuclear Reactors - Presentation by Nuclear Energy Institute and Us Nuclear Industry Council ML21335A2602021-12-0202 December 2021 ROP Public Meeting Gtg PI 12022021 ML21334A3562021-11-29029 November 2021 Fire Protection-ROP Public Meeting-120221 ML21223A1002021-08-11011 August 2021 NEI Slides for Public Meeting on Reg Guide 1.9, Rev.5 - Revised 8-11 ML21221A2962021-08-11011 August 2021 NEI Slide Presentation on Regulatory Guide 1.9, Revision 5 for Public Meeting August 11, 2021 ML21187A0572021-07-0707 July 2021 July 7 Public Mtg Slides for Pre-application of NEI 16-03 & EPRI i-LAMP ML21173A0562021-06-22022 June 2021 NEI Presentation - Adversary Timeline Methodology (Final- 6.24.21) - Updated ML21173A2862021-06-21021 June 2021 NEI 20-07 Systematic Approach to CCF NRC 2024-01-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24016A2372024-01-17017 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 ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23117A3712023-05-0202 May 2023 NEI Lessons Learned Meeting Slides, May 2, 2023 ML23115A0302023-04-27027 April 2023 NEI Perspective on Performance Monitoring in Use of Probabilistic Fracture Mechanics for Optimizing Inspections of Non-RPV Pressure Vessels, April 27, 2023 ML23088A0822023-03-30030 March 2023 NEI Presentation - March 30, 2023 PRA Configuration Control Public Meeting ML23082A0572023-03-28028 March 2023 Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk ML23079A2642023-03-23023 March 2023 General Visual Examination of Containment Surfaces Covered by Insulation - March 23, 2023 Public Meeting Slides from NEI ML23210A0042023-03-15015 March 2023 Destination: Termination, NRC Regulatory Information Conference ML23045A2892023-03-14014 March 2023 RIC 2023 - 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric).Operational and Safety Benefits of Risk Informed Applications ML23061A0292023-03-0202 March 2023 NEI Presentation - Advanced Reactor Digital I&C Licensing Workshop 1 ML23013A0782023-01-13013 January 2023 PI&R Inspection Discussion for January 2023 ROP Public Meeting ML23012A1382023-01-12012 January 2023 General Visual Examination of Containment Surfaces Covered by Insulation - 1/19/23 Public Meeting Slides from NEI ML23041A4342022-12-15015 December 2022 NEI Presentation for December 15, 2022 Industry Spent Fuel Activities Prioritization Meeting ML22333A7192022-11-29029 November 2022 NEI-Presentation-Seismic Hazards Public Meeting - November 2022 - Final Presentation to NRC ML22318A3032022-11-16016 November 2022 NEI-22-01 License Termination Process Pre-Submittal Meeting November 16, 2022 (Presentation) ML22291A4442022-10-11011 October 2022 NEI 22-01 License Termination Plan Process Presentation at October 11 2022 Meeting on NUREG-1757 Vol. 2 ML22250A7122022-09-21021 September 2022 NEI 22-03 Presentation Slides for NRC Public Meeting (Sept. 21, 2022) ML22235A7032022-08-24024 August 2022 NEI Presentation for Aug 26, 2022 Public Meeting - Source Terms and Radiological Consequence Analyses ML22216A1152022-08-0404 August 2022 August 4, 2022 Rislr Public Meeting Presentation by Nuclear Energy Institute ML22194A0682022-07-18018 July 2022 NEI Presentation for NEI 22-02 Rsi Response ML22174A2822022-06-22022 June 2022 NEI Presentation for Public Meeting with NMMSS Users Community to Discuss Foreign Obligation Reporting Requirements for Low Enriched Uranium ML22172A1352022-06-21021 June 2022 NEI Presentation for Public Meeting Industry Perspectives on Rulemaking for Greater than 5 Percent Enrichment ML22152A0942022-06-0202 June 2022 NEI Slides - Risk Insights for Aging Management Presentation June 2, 2022 ML22143A8542022-05-20020 May 2022 Nuclear Energy Institue (NEI) Presentation Slides to ACRS Subcommittee on CCF Secy Paper, May 20, 2022 ML22164A0182022-05-18018 May 2022 Fuel Cycle Industry NRC Fcf Stakeholders Mtg May 2022 ML22124A2072022-05-13013 May 2022 Public Meeting Slides for May 13 2022 CRGR Meeting Regarding RIS on Operating Leakage ML22136A1162022-05-11011 May 2022 Presentation 5 - Utilizing the Nuclear Energy Institute (NEI) 07-07 Industry Groundwater Protection Initiative as a Foundation for Addressing Subsurface Site Assessments ML22102A2022022-04-12012 April 2022 NEI Presentation Related to the Development of Adversary Timelines NRC Comment Resolution ML22053A2802022-03-31031 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - True D - NEI Presentation RIDM Greater than Sum of Its Parts ML22088A0342022-03-29029 March 2022 Public Meeting Presentation by NEI Regarding Part 53 Rulemaking: Selected Topics ML22077A4012022-03-23023 March 2022 NEI INL Presentation March 23, 2022, NRC Workshop Isv Hfe Issue 2024-01-09
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NEI 20-07 Guidance for Addressing CCF in High Safety Significant Safety-related DI&C Systems July 1, 2021
©2021 Nuclear Energy Institute
Addressing HSSSR Systematic CCF BTP 7-19, Rev. 8 allows for NRC-approved alternative methods, including defensive measures, in the design of a system or componentthat may eliminate a potential CCF from further consideration.
BTP 7-19, Section 3.1.3: Licensees may propose technical approaches to address CCF that this BTP does not describeThe NRCs approval of an alternative method should include a supporting technical basis and acceptance criteria for its use.
The approach described in this presentation is intended to fall under these statements in BTP 7-19
©2021 Nuclear Energy Institute 2
Addressing HSSSR Systematic CCF Two step process Step 1
- Perform a systematic hazards analysis based on STPA that creates a model of the system control structure and identifies unsafe control actions
- Establish a Risk Reduction Objective (RRO)
Step 2
- Develop STPA loss scenarios based on Step 1
- Identify and allocate systematic control methods to eliminate or mitigate loss scenarios
- Score control methods to achieve a sufficient effectiveness commensurate with the RRO
©2021 Nuclear Energy Institute 3
Step 1: Hazard Analysis & Establishing Risk Reduction Objective (RRO)
Addressing HSSSR Systematic CCF - Step 1 Hazard Analysis IEC 61508-1 requires a determination of hazards of the Equipment Under Control (EUC) and the EUC control system, and consideration shall be given to the elimination or reduction of the hazards. NEI 20-07 uses the first 3 parts of the STPA hazard analysis method in this first step of the process.
Identify losses Identify system hazards that contribute to losses Create control system model (control structure) and identify unsafe control actions (UCAs)
©2021 Nuclear Energy Institute 5
Addressing HSSSR Systematic CCF - Step 1 Unsafe control actions The STPA handbook explains that for each control action linked to a hazard, four cases need to be analyzed:
Not providing the control action causes the hazard Providing the control action causes the hazard Providing the control action too late or out of order causes the hazard Providing the control action too long or stopped too soon
©2021 Nuclear Energy Institute 6
Addressing HSSSR Systematic CCF - Step 1 Establish RRO Create bounding assessment:
calculate the change in risk from the baseline PRA model when the entire HSSSR system fails The delta risk is then mapped to the regions described in RG 1.174 The delta risk is used to determine the RRO
©2021 Nuclear Energy Institute 7
Addressing HSSSR Systematic CCF - Step 1 Establish RRO (cont.)
Establish RRO band (A-D)
Risk Reduction Objectives
©2021 Nuclear Energy Institute 8
Addressing HSSSR Systematic CCF - Step 2 Develop STPA loss scenarios based on Step 1 Identify and allocate systematic control methods to eliminate or mitigate loss scenarios Score control methods to achieve a sufficient effectiveness commensurate with the RRO
©2021 Nuclear Energy Institute 9
Addressing HSSSR Systematic CCF - Step 2 Develop STPA loss scenarios based on Step 1
What is a Loss Scenario?
Loss Scenario - describes the causal factors that can lead to the unsafe control actions (that lead to hazards).
Loss scenarios are reasons why a UCA can manifest itself, or reasons why a control action is not executed or executed improperly.
Two types of loss scenarios Why would Unsafe Control Actions occur?
Why would control actions be improperly executed or not executed, leading to hazards?
©2021 Nuclear Energy Institute 11
Loss Scenario Types from STPA Handbook
©2021 Nuclear Energy Institute 12
Loss Scenarios For each UCA developed from the hazard analysis, loss scenarios are created that can be sourced from:
Unsafe controller behaviors Inadequate feedback and information Failures in control paths Failures in controlled processes For each loss scenario, systematic control methods are developed to eliminate or mitigate the loss scenario
©2021 Nuclear Energy Institute 13
Loss Scenario Sources Unsafe controller behaviors Failures in control Inadeqate feedback paths and information Failures in controlled processes
©2021 Nuclear Energy Institute 14
Addressing HSSSR Systematic CCF - Step 2
- Develop STPA loss scenarios based on Step 1
- Identify and allocate systematic control methods to eliminate or mitigate loss scenarios
- Score control methods to achieve a sufficient effectiveness commensurate with the RRO
©2021 Nuclear Energy Institute 15
Identify and allocate systematic control methods to eliminate or mitigate loss scenarios What is a systematic control method?
They are methods that can be implemented to eliminate or mitigate a loss scenario The identification of systematic control methods suitable for any given loss scenario is highly dependent on the characteristics of the loss scenario itself For each systematic loss scenario, the assessment identifies what systematic control method or methods to apply to eliminate or mitigate the loss scenario
©2021 Nuclear Energy Institute 16
Identify and allocate systematic control methods to eliminate or mitigate loss scenarios Allocate control methods to the system elements in the HSSSR system A control method could be solely applied to one element in the HSSSR system (e.g., a particular controller)
A control method may need to span multiple elements in the HSSSR system to be fully applied (e.g., multiple controllers or controller and equipment under control)
©2021 Nuclear Energy Institute 17
Addressing HSSSR Systematic CCF - Step 2
- Develop STPA loss scenarios based on Step 1
- Identify and allocate systematic control methods to eliminate or mitigate loss scenarios
- Score control methods to achieve a sufficient effectiveness commensurate with the RRO
©2021 Nuclear Energy Institute 18
Score control methods to achieve a sufficient effectiveness commensurate with the RRO A scoring method is used as a qualitative approach to assess control method effectiveness There are two parts to this process:
Part 1:
Apply pre-scored systematic control methods for the control algorithm commensurate with the RRO (adapted from IEC 61508, e.g., Annex A in Part 3)
These are techniques and measures that need to be followed commensurate with the RRO
©2021 Nuclear Energy Institute 19
Score control methods to achieve a sufficient effectiveness commensurate with the RRO Scoring Part 2:
Score the balance of the systematic control methods that eliminate or mitigate loss scenarios Each control method is scored for its type and each control method is scored for its strength It is the combination of the control method type and strength that provides an assessment of control method effectiveness
©2021 Nuclear Energy Institute 20
Score control methods to achieve a sufficient effectiveness commensurate with the RRO The are two characteristics to a control method that eliminated or mitigated a loss scenario Control Method Type (e.g., administrative, procedure, technical, etc.)
Control Method Strength (e.g., the degree to which control method can prevent, detect, respond, and recover from a loss scenario before the UCA occurs)
©2021 Nuclear Energy Institute 21
Score control methods to achieve a sufficient effectiveness commensurate with the RRO The scoring methodology uses elements of standard information theory, and in particular the key measure of entropy Entropy is a measure of the information content in a system.
When each piece of information is defined, a log base 2 equation is used to measure the combined information content.
Control method information, defined by its type and strength, is combined using the log base 2 approach to provide a scoring for its overall effectiveness Its a way to provide a defined scale for the qualitative assessment of control method effectiveness ©2021 Nuclear Energy Institute 22
Score control methods to achieve a sufficient effectiveness commensurate with the RRO The control method effectiveness score is compared to RRO benchmark for control method effectiveness This provides a means to assess if the control method effectiveness is commensurate with the RRO If the control method effectiveness is not commensurate with the RRO then NEI 20-07 will describe considerations to increase control method effectiveness.
©2021 Nuclear Energy Institute 23
Summary and Conclusion Summary and Conclusion This NEI 20-07 approach to addressing CCF is based on assessing the potential risk of the HSSSR system replacement and the necessary control methods to lower the risk to non-risk significant It is a 2-step process that establishes an objective based on risk insights and control methods commensurate to achieve a risk reduction objective The NEI 20-07 approach falls under alternative methods as described in BTP 7-19 (p. 19-8) to addressing HSSSR system CCF that is risk informed and performance based A traceability record is created tracing the losses, hazards, UCAs, loss scenarios, and control methods to mitigate loss scenarios
©2021 Nuclear Energy Institute 25
Proposed Schedule July 1, 2021 - Present NEI 20-07 systematic approach to addressing CCF August 31, 2021 - NEI draft revision of NEI 20-07 incorporating NRC feedback September 30, 2021 - Peer review and industry feedback on NEI 20-07 draft revision October 29, 2021 - Submit NEI 20-07 draft revision for NRC feedback November 30, 2021 - Public meeting to obtain This Photo by Unknown Author is licensed under CC BY-NC NRC feedback Q1 2022 - NEI 20-07 submittal for NRC formal endorsement ©2021 Nuclear Energy Institute 26