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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 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 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 ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection 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
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 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 - 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[Table view] |
Text
DG-1327 ClarificationReactivity Initiated Accident GuidanceT. W. EichenbergEPRI Fuel Reliability Program, Reg
-TAC ChairSr. Specialist Reactor Safety Analysis, TVAJanuary 25, 2017 *White Flint, Rockville MD 1
Overview*Categories for Discussion
-Methods & Assumptions
-Failure Thresholds
-Release Fractions
-Miscellaneous 2
PWR vsBWRPerspectiv e*While Rod Eject / Blade Drop are Reactivity Initiated Accidents-
-These different events don't share an identical topology
- Analytical space is different
-Every assumption isn't automatically meaningful to both PWR's and BWR's-Example from item 2.2.5
- (b) is BWR speak-Example item 2.2.10
Methods & Assumptions
-What does "account for calculational uncertainties mean"?
-Realistic / Risk Informed methods to be allowed?-Expecting a full RG 1.203 process?
4 Methods & Assumptions
- 5% power DNB/CPR threshold?
-Value is below TS monitoring power level.
- Correlation range of applicability may not extend that low
-DNB/CPR may not be appropriate metric relative to very fast transient condition 5
Methods & Assumptions
-Are "sensitivity" studies going to be plant and cycle specific?
-What is NOT a "major reactivity feedback?"
- Direct Moderator HeatingNon-Eq. T-H-What is meant by "manufacturing tolerances?"
- Plant , fuel type, and/or cycle specific.As-built vs bounding tolerance
-Accounting for something vs. sensitivity/parametric evaluation.
6 Methods & Assumptions
-What is meant by "wider operating conditions"?
-Effectively, you're saying the determination of limiting conditions is non
-linear.*When does the search stop? To "survey a larger population" implies a realistic assessment.
-What is "sufficient parametric study"?
7 Methods & Assumptions
-Why do advanced methods need to implement artificial conservatism to compare against failure criteria?
-Extensive focus on bounding assumptions
- Seems incompatible with implications of 2.2.4 (limiting scenario tied to non
-linear effects, not artificial conservatisms) 8 Methods & Assumptions
-Approved hydrogen pickup model is explicit
-Need for an approved hydride orientation model is not as obvious. Need to validate the failure curve utilized.-Is the use of RG 1.224 account for hydride orientation issue?
9 Failure Thresholds
-Why Revision 1
- MBT Data / NSRR corrections
-Temperature Effects
-Pulse Effects
-Power History Effects
-Hydrogen > 300ppm
-Elongation
-FailureLimit s 10http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000003002005540 Failure Thresholds
-Yes, in the sense that curve fits are relative to nominal data.
-No, in the sense that the shape of curve fits displays negative impact in areas without failures*Low Hydrogen region
-No, in the sense that correlation coefficients are in some casessubstantiallylessthan 1 11 Release Fractions
-Keep information in one place; remove from DG
-1327-Locate to 1.183, 1.195, etc. (sign of a bigger problem)*Example: Changing dose method constitutes an AST/TID backfit?
12 Release Fractions
- Transient Fission Gas Release-Database doesn't represent low burnup 13 Miscellaneous
-Approved Analytical Methods must Exist
- Method reviews in a timely manner?
- Potential New Method Elements
-Transient Fission Gas Release / Mechanical aspect
-Corrosion/Hydrogen Uptake/Crud
-Hydride Characterization
-FCI Impact if Centerline Melt Allowed
-Contribution of Fission Gas Release to Pressure Surge 14 Questions?? / Discussion 15