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Category:Meeting Briefing Package/Handouts
MONTHYEARML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - NEI Slides ML24229A0012024-08-19019 August 2024 NEI - Spent Fuel Management: Safety and Efficiency Improvements Through Technology and Performance Margins - NRC PIRTs Public Meeting Rev. 8.15.2024 Final ML24218A1832024-07-30030 July 2024 NEI 7-30-24 Trial Use RG 1.247 Path Forward Final ML24172A1952024-06-27027 June 2024 NEI Slides for 06-27-2024 Public Meeting Structures as IROFS at Fuel Cycle Facilities ML24178A0372024-06-26026 June 2024 NRC Power Uprate Review Preparation June 26, 2024 Public Meeting Slides ML24164A1972024-06-17017 June 2024 Public Meeting Slides - NRC Staff Comments and Observations on NEI 10-01, Rev 2 Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit ML24129A1382024-05-0808 May 2024 NEI Slides on Centralized Inspections for May 9, 2024 Public Workshop ML24103A1532024-04-12012 April 2024 NEI Supplemental Information on NRC Comments of NEI 20-07 Rev E (Non-Proprietary) - Slides ML24088A2252024-03-26026 March 2024 NEI Slides for Centralized Inspections March 2024 ROP Public Meeting ML24075A2092024-03-14014 March 2024 NEI Advanced Reactor Di&C Task Force Slides - Accident Monitoring Instrumentation ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24067A0062024-03-0808 March 2024 1 - 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 ML24016A2372024-01-17017 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 2024-08-20
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - NEI Slides ML24229A0012024-08-19019 August 2024 NEI - Spent Fuel Management: Safety and Efficiency Improvements Through Technology and Performance Margins - NRC PIRTs Public Meeting Rev. 8.15.2024 Final ML24218A1832024-07-30030 July 2024 NEI 7-30-24 Trial Use RG 1.247 Path Forward Final ML24197A0652024-07-17017 July 2024 SDP Realism Public Meeting NEI Presentation ML24172A1952024-06-27027 June 2024 NEI Slides for 06-27-2024 Public Meeting Structures as IROFS at Fuel Cycle Facilities ML24178A0372024-06-26026 June 2024 NRC Power Uprate Review Preparation June 26, 2024 Public Meeting Slides ML24164A1972024-06-17017 June 2024 Public Meeting Slides - NRC Staff Comments and Observations on NEI 10-01, Rev 2 Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit ML24130A1972024-05-0909 May 2024 NEI Presentation Slides on Rapid and Large-Scale Nuclear Reactor Deployments for Remote Industrial Applications - May 14 2024 Public Meeting ML24129A1382024-05-0808 May 2024 NEI Slides on Centralized Inspections for May 9, 2024 Public Workshop ML24114A1142024-04-18018 April 2024 NEI Supplemental Information on NRC Comments on NEI 20-07, Draft Revision E - April 18 Meeting (Non-Proprietary) ML24103A1532024-04-12012 April 2024 NEI Supplemental Information on NRC Comments of NEI 20-07 Rev E (Non-Proprietary) - Slides ML24092A3132024-04-0303 April 2024 Public Mtg_2024-04-03 Pre-submittal Meeting with the Nuclear Energy Institute (NEI) to Discuss an Update to NEI 03-12, Security Plan Template (Revision 8)_NEI Slides ML24088A2252024-03-26026 March 2024 NEI Slides for Centralized Inspections March 2024 ROP Public Meeting ML24075A2092024-03-14014 March 2024 NEI Advanced Reactor Di&C Task Force Slides - Accident Monitoring Instrumentation ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24082A1792024-03-14014 March 2024 RIC-2024 TH18 True Slides ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24067A2592024-03-13013 March 2024 RIC-2024 W14 Slides - NEI-BHoltzman an Industry Perspective on Advanced Reactor Construction Oversight ML24067A0062024-03-0808 March 2024 1 - 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 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 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 2024-08-20
[Table view] |
Text
Workshop #1 Advanced Reactor Digital I&C Licensing February 23, 2023
©2023 Nuclear Energy Institute
Industry Team Overview Representation from:
- 8 Advanced Reactor Vendors
- 4 Licensing Consultant Firms
- 2 Industry Groups (including NEI)
Maintaining communication with NEI Digital I&C task forces and executive working group Regular meetings to identify generic issues and questions
©2023 Nuclear Energy Institute 2
Licensing Modernization and Design Review Guide
Questions - Design Review Guide Design Review Guide (DRG): Instrumentation and Controls for Non-Light-Water Reactor (Non-LWR) Note 1 states:
The DRG was developed to address the immediate needs associated with the non-LWR community. Since the DRG is technology inclusive, it may be used for the review of LWR plant designs and other reactor technologies.
Question 1: Please clarify any dependencies between NUREG-0800 (or NUREG-1537) and the DRG. Our understanding is the DRG is mutually exclusive of any other review guidance.
Question 2: For Advanced Reactor designs that are considered LWR plant designs, please provide clarification whether there are any restrictions to the use of the DRG.
©2023 Nuclear Energy Institute 4
Questions - Licensing Basis Events NEI 18-04 Section 3.2.2, Task 5a provides direction to assign a Required Safety Function(s) (RSF) for high-consequence Beyond Design Basis Events (BDBEs). Task 5b further states:
SR SSCs are also selected for any RSF associated with any high-consequence BDBEs in which the reliability of the SSC is necessary to keep the event in the BDBE frequency region.
DRG Section X.2.2.1.3, Point 4 states:
Equipment that is not safety-related can be used to provide the diverse means provided it is of sufficient quality to perform the necessary function under the associated event conditions in a reliable manner.
©2023 Nuclear Energy Institute 5
Questions - Licensing Basis Events Question 1: LMP (and NEI 18-04 Figure 3-1, right) requires a quantitative PRA approach to determine Licensing Basis Events (LBEs); however, there is no consensus standard for determining software reliability quantitatively. Overly conservative quantitative values may result in the mis-classification of LBEs and/or associated SSC safety classification. Does the NRC plan to provide guidance on how to consider software reliability in the LBE selection process?
©2023 Nuclear Energy Institute 6
Questions - Licensing Basis Events Common Cause Failure (CCF) is considered a high-consequence BDBE; however, SRM-SECY-93-087, BTP 7-19, and the DRG allow the use of non-safety related equipment as diverse means to mitigate CCF of the safety-related I&C system.
Question 2: The LMP process presents use-cases where safety-related SSCs may be required to mitigate CCF; however, Commission policy, and current practice among operating LWR plants, categorically allows the use of non-safety-related SSCs (SRM-SECY-93-087 Positions 3 and 4). Can non-safety functions be used to mitigate the effects of CCF as is currently implemented among operating LWR plants? Provide clarification regarding the acceptance criteria for strategies used to address CCF, such as diversity, and associated safety classification.
©2023 Nuclear Energy Institute 7
Questions - Non-Safety-Related Special Treatment For Non-Safety-Related Special Treatment (NSRST), the DRG Section X.0.1.1, Scope of Review, states:
This DRG chapter provides review guidance on all aspects of safety-significant I&C systems, which include safety-related I&C systems and I&C systems that are not safety-related but warrant special treatment.
However, NSRST criteria are specified by name in various sections, such as:
- Appendix A System Characteristics
©2023 Nuclear Energy Institute 8
Questions - Non-Safety-Related Special Treatment Question 1: Are NSRST criteria limited to the sections that are specified, or should the entirety of the DRG be considered?
Question 2: DRG Appendix A provides clarification or re-emphasizes design criteria from IEEE Std 603. LMP primarily focuses its guidance for NSRST SSCs on process, not design criteria. Our understanding is that a vendor should select appropriate DRG Appendix A design criteria that support their reliability and robustness claims associated with the NRSRT function(s).
Question 3: Does NRC staff have Quality Assurance requirements/acceptance criteria established for NSRST SSCs?
©2023 Nuclear Energy Institute 9
Questions - Non-Safety-Related Special Treatment Question 4: Per NEI 18-04 Section 4, NSRST SSCs can be classified as relied on to perform risk-significant functions or requiring special treatment for DID adequacy. Are special treatments differentiated between the two categories of NSRST SSCs? For example, are NSRST SSCs required for DID adequacy required to address single failure criterion, diversity, etc.?
©2023 Nuclear Energy Institute 10
Alternative Frameworks Questions - Alternative Frameworks In determining I&C design criteria required to prevent or mitigate the effects of Anticipated Operational Occurrences, SRP Chapter 15 Section I.4 states:
The reviewer ensures that the application lists the settings of all the protection and safety systems functions that are used (i.e., credited) in the safety evaluation.
Typical protection and safety systems functions include reactor trips, isolation valve closures, ECCS initiation and ECCS. In evaluations of AOOs and postulated accidents, the performance of each credited protection or safety system is required to include the effects of the most limiting single active failure.
NEI 18-04 Table 3-1 states:
AOOs take into account the expected response of all SSCs within the plant, regardless of safety classification.
©2023 Nuclear Energy Institute 12
Questions - Alternative Frameworks Historically, there has been a perception that an applicant needs a safety-related system, instead of a set of anticipatory and/or non-safety SSCs, in order to meet AOO acceptance criteria.
Question 1: If a vendor proposes to use an alternative framework, can that vendor credit the expected response of all SSCs within the plant (e.g., other than safety-related instrumentation and controls), regardless of safety classification?
©2023 Nuclear Energy Institute 13
Questions - Alternative Frameworks Question 2: If the vendor is able to credit the expected response of all SSCs within the plant, this will impact the selection and wording of Principal Design Criteria. Are there any specific considerations that vendors should be aware of when applying this concept?
For example, 10 CFR 50, Appendix A GDC 20 states:
Protection system functions. The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.
The highlighted words may be defined and executed differently in different frameworks. ©2023 Nuclear Energy Institute 14
NRC Question Clarification Remote, Monitoring, and Control How does the NRC define Rooms. To what extent will remote? For example, is advanced reactors employ remote outside of the Main Control monitoring of the plant for Room considered remote.
operational purposes? How could How does the NRC define the design of I&C safety systems and autonomous? Is the NRC control systems be impacted by the implying the use of Artificial increased use of autonomous Intelligence for control system operations? response to a non-specified event?
©2023 Nuclear Energy Institute 15
Future Topics Industry Responses to NRC proposed questions
- Currently aggregating responses Other Topics:
- Application Format/Contents
- Additional guidance/clarity for:
Digital Technologies Model-Based V&V Self-Diagnostics Transitioning from LMP to Design Requirements
©2023 Nuclear Energy Institute 16