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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 - 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[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 - 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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 - 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Text
Low Safety Significance Issue Resolution (LSSIR)
Andrew Mauer Director, Regulatory Affairs Greg Kreuger Senior Technical Advisor August 7, 2019
©2019 Nuclear Energy Institute
Introduction Industry recognizes the importance of maintaining compliance with requirements.
At the same time, we believe that safety significance can be used to inform the resolution of issues where there is not a clear non-compliance, as well as to inform the methods used to restore compliance.
A relatively simple and repeatable process is necessary to enable the safety significance to be understood early in the life cycle of a regulatory issue, and that issue resolution flows logically from that evaluation.
©2019 Nuclear Energy Institute 2
Foundational Characteristics of LSSIR Process Process needs to allow for evaluation of safety significance early in the life cycle of the issue - before the expenditure of substantial resources.
Where appropriate, issues of low safety significance, that are not a matter of compliance (lower left quadrant), should be dispositioned via no further action, with durable documentation.
Process should provide a mechanism for staff to promptly escalate issues to aid in determining both: (1) whether the safety significance evaluation should be applied, and, if so, (2) whether additional resources should be devoted to an issue based on safety significance.
©2019 Nuclear Energy Institute 3
©2019 Nuclear Energy Institute 4 Assessing Safety Significance Qualitative Quantitative Considerations Considerations Potentially Safety Potentially Safety Significant Significant Fundamental Criteria
- Potential Consequence safety goal screening criteria
- Consider TEC-002 for Considerations refined semi-qualitative and quantitative risk criteria
- Scope of issue Not Safety Significant
- Evaluate the change or Proceed
- Potential for mitigating delta risk between options with Issue actions or compensatory or different resolutions measures associated with Disposition temporary conditions Document Decision
©2019 Nuclear Energy Institute 5
Qualitatively Assessing Safety Significance A qualitative assessment is essential to drive an initial evaluation of safety across a wide variety of potential issues
- Not all issues are amenable to quantification or application of existing models/tools Fundamental Criteria
- Likelihood and Potential Consequence both need to be considered High for an issue to be identified as Potentially Safety Significant
©2019 Nuclear Energy Institute 6
Alignment with Principles of Risk Informed Decision Making Compliance with current regulations Consistency with the defense-in-depth (DID) philosophy Maintaining adequate safety margins Demonstrating acceptable levels of risk, along with a feedback or oversight function to assure consistency across the breadth of regulatory issues and organizations
©2019 Nuclear Energy Institute 7
Integrated and Holistic Approach Provides a method to assess safety significance and determine if additional resources or analysis to be applied to reach a conclusion.
This series of questions are not intended to drive a detailed risk evaluation when documenting the basis for the response to each question.
Most closely aligned with issues that impact initiating event, mitigating systems, or barrier cornerstones
©2019 Nuclear Energy Institute 8
Assessing Likelihood L1. Does the impact of an issue have the potential to create a new initiating event or change the frequency of an initiating event (Licensing Basis Event) that is similar to that of an Anticipated Operational Occurrence (AOO)? If yes, the issue should be considered significant from a likelihood perspective.
L2. Does the issue or proposed change significantly increase the likelihood of a cause or event that could create simultaneous mitigation challenges with respect to equipment or operator response? If yes, the issue should be considered significant from a likelihood perspective.
L3. Does the scope of the potential issue significantly impact or increase the likelihood of an event across SSCs, functions, or units at a site? If yes, the issue may be considered significant from a likelihood perspective. ©2019 Nuclear Energy Institute 9
Assessing Likelihood (Continued)
Responses to the likelihood questions can be (1) significant, (2) not significant, or (3) not applicable.
A response of significant to any of these questions, would result in the likelihood being characterized as significant.
In addition, the consideration of issues extent of condition potential to multiple SSCs or plant functions, or multiple units at a site could be initially considered Significant given the potential broad implications of an issue.
©2019 Nuclear Energy Institute 10
Assessing Potential Consequences C1. Does the issue have the potential to significantly impact or change the potential consequences associated with an event? If yes, the issue should be considered significant from a consequence perspective.
C2. Does the issue impact multiple aspects of mitigation capability or a defined fission product barrier? If yes, the issue should be considered significant from a consequence perspective.
C3. Could the issue significantly diminish evaluated safety margins? If yes, the issue should be considered significant from a consequence perspective.
©2019 Nuclear Energy Institute 11
Assessing Potential Consequences (Continued)
C4. Does the issue create a significant shift from mitigation systems to operator response or significantly increase operator response burden?
If yes, the issue should be considered significant from a consequence perspective.
C5. Does the scope of the potential issue significantly impact or increase the mitigation capability or potential consequences across SSCs, functions, or units at a site? Qualitative consideration of the protection in aggregate at the site should be accounted for when assessing the extent of condition of an issue. If yes, the issue may be considered significant from a consequence perspective.
©2019 Nuclear Energy Institute 12
Assessing Potential Consequences (Continued)
Responses to the potential consequence questions can be (1) significant, (2) not significant, or (3) not applicable.
A response of significant to any of these questions, would result in the potential consequences being characterized as significant.
Note: One unique aspect considered in the consequence questions is associated with the ability to mitigate the identified potential consequence using process, plant changes, or configuration controls.
- Clearly the consequence would not be considered significant if mitigation or elimination of the consequence can be employed after the issue is identified. Further consideration of such controls and the length of time mitigation of the issue may be warranted.
©2019 Nuclear Energy Institute 13
Overall Results It is envisioned that both the likelihood of the issue and the potential consequence of an issue would need to be qualitatively characterized as Significant for the issue to move forward toward a more quantitative evaluation.
Employing additional and cross-functional personnel resources would ultimately be applied to a particular issue if the initial qualitative determination is potentially safety significant.
©2019 Nuclear Energy Institute 14
Conclusion We appreciate the NRCs continued leadership and focused attention on low safety significance issue resolution
©2019 Nuclear Energy Institute 15