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Category:Meeting Briefing Package/Handouts
MONTHYEARML24347A2052024-12-0202 December 2024 ASME Code Case N-860 and Reg Guide 3.78 Nei/Industry Perspective ML24328A0012024-11-25025 November 2024 NEI Presentation Slide 11-22-2024 N-921 Exemption Request Template Draft ML24327A1782024-11-22022 November 2024 NEI Lofg Presentation on Use of Glass Top Simulators ML24318C4532024-11-14014 November 2024 Power Uprate November 14 2024 NEI Public Meeting Slides - Industry Perspectives on Combined License Applications – Improved Efficiencies & Agility ML24320A1202024-11-13013 November 2024 NEI Slides for November 13, 2024 Fuel Facilities Stakeholder Meeting ML24310A2262024-11-0606 November 2024 NEI Preliminary Perspectives on NRC Draft Noak Microreactor White Paper ML24303A2212024-10-29029 October 2024 NEI SDP Realism Presentation for October 30, 2024 Public Meeting ML24291A0062024-10-17017 October 2024 NEI Slide Presentation: ACRS Regulatory Policies and Practices - Draft White Paper on Nth-of-a-Kind (Noak) Micro-Reactor Licensing and Deployment Considerations - Sc - October 17, 2024 ML24267A0032024-09-25025 September 2024 NEI Slides for ROP Public Meeting Sept 2024 ML24263A2592024-09-17017 September 2024 06 Jim Slider NEI September 2024 NRC Ai Public Workshop 09-17-2024 ML24249A2012024-09-0909 September 2024 NEI Presentation - Sept 9 Public Meeting - Flooding DGs - Final ML24249A1152024-09-0505 September 2024 Power Uprate September 5, 2024 Public Meeting Slides ML24243A1612024-08-30030 August 2024 Slide Presentations for High Burnup (Hbu) Workshop V ML24228A2102024-08-20020 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 ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A0092024-03-0808 March 2024 3 - NRC - Worshop3 - CR Dose Presentation - Final ML24067A0062024-03-0808 March 2024 1 - NRC - Workshop3 - Non-LOCA Release Fractions Feedback - Final ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0072024-03-0808 March 2024 2 - NRC - Workshop3 - Non-LOCA - FFRD - Final ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24043A1162024-02-13013 February 2024 3- EQ 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 ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation 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 2024-09-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24347A2052024-12-0202 December 2024 ASME Code Case N-860 and Reg Guide 3.78 Nei/Industry Perspective ML24328A0012024-11-25025 November 2024 NEI Presentation Slide 11-22-2024 N-921 Exemption Request Template Draft ML24327A1782024-11-22022 November 2024 NEI Lofg Presentation on Use of Glass Top Simulators ML24319A2522024-11-20020 November 2024 ACRS External ACRS Meeting November 20, 2024, NEI View on Artificial Intelligence ML24318C4532024-11-14014 November 2024 Power Uprate November 14 2024 NEI Public Meeting Slides - Industry Perspectives on Combined License Applications – Improved Efficiencies & Agility ML24320A1202024-11-13013 November 2024 NEI Slides for November 13, 2024 Fuel Facilities Stakeholder Meeting ML24310A2262024-11-0606 November 2024 NEI Preliminary Perspectives on NRC Draft Noak Microreactor White Paper ML24303A2212024-10-29029 October 2024 NEI SDP Realism Presentation for October 30, 2024 Public Meeting ML24291A0062024-10-17017 October 2024 NEI Slide Presentation: ACRS Regulatory Policies and Practices - Draft White Paper on Nth-of-a-Kind (Noak) Micro-Reactor Licensing and Deployment Considerations - Sc - October 17, 2024 ML24267A0032024-09-25025 September 2024 NEI Slides for ROP Public Meeting Sept 2024 ML24263A2592024-09-17017 September 2024 06 Jim Slider NEI September 2024 NRC Ai Public Workshop 09-17-2024 ML24249A2012024-09-0909 September 2024 NEI Presentation - Sept 9 Public Meeting - Flooding DGs - Final ML24249A1152024-09-0505 September 2024 Power Uprate September 5, 2024 Public Meeting Slides ML24243A1612024-08-30030 August 2024 Slide Presentations for High Burnup (Hbu) Workshop V ML24228A2102024-08-20020 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 ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24082A1792024-03-14014 March 2024 RIC-2024 TH18 True Slides ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24067A2592024-03-13013 March 2024 RIC-2024 W14 Slides - NEI-BHoltzman an Industry Perspective on Advanced Reactor Construction Oversight ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks 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 ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24043A1162024-02-13013 February 2024 3- EQ 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 2024-09-09
[Table view] |
Text
©2024 Nuclear Energy Institute Greg Broadbent, Senior Staff Engineer -
Corporate Nuclear Analysis, Entergy (Retired)
Sam Lafountain, Lead Engineer, Southern Nuclear Alex Markivich, Engineer III, Dominion Energy Frankie Pimentel, Sr. Project Manager -
Engineering & Risk, NEI February 13, 2024 Impact of SAND2023-01313 on Source Terms and Radiological Consequence Analyses
©2024 Nuclear Energy Institute 2 Increased Release Fractions can have wide-ranging impacts on plant safety analyses Examples will include results from Dose Impacts for 2 BWRs (Mark I and Mark III) 2 PWRs (large dry and subatmospheric)
Examples of Impacts
©2024 Nuclear Energy Institute 3 What is changed?
RG 1.183 Rev. 1 and SAND2023-01313 release fractions and durations Longer release durations necessitate changes to spray removal effectiveness or duration Worst-case X/Q corresponding to period of highest release Assessment of pool scrubbing for BWRs, as described in SAND2023-01313 Table 5-16 What was NOT changed Core inventory (Ci/MW)
Dose Evaluation Changes
©2024 Nuclear Energy Institute 4 Example 1: BWR/6, Mark-III Containment BWR/6, Mark-III Containment Standard Leakage Paths
- No credit for MSL deposition past the outboard MSIV
- Credit for MSIV Leakage Control System initiation at 20 minutes 99% SGTS filters, ~1 hour holdup
©2024 Nuclear Energy Institute 5 Example 1: BWR/6, Mark-III - Model Changes
Drywell-Containment Mixing Current RG 1.183, Rev. 0 accepted uniform mixing after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Changed to only credit 2000-cfm hydrogen purge system for entire period See Resolution to Comment 6-5 from the BWROG
©2024 Nuclear Energy Institute 6 Example 1: BWR/6, Mark-III Containment - Results 9.71 6.20 4.11 6.62 5.81 4.49 4.56 4.16 2.90 8.15 6.44 5.50 5.1 4.41 3.55 0
2 4
6 8
10 12 Exclusion Area Boundary Low Population Zone Control Room Dose (Rem TEDE)
Location Offsite & Control Room Doses Reg Guide 1.183 Rev. 0 Rev. 1 Rev. 1 w/pool SAND2023-01313 SAND2023-01313 w/pool
©2024 Nuclear Energy Institute 7 Example 1: BWR/6, Mark-III Containment - Conclusions
Impact of New Mixing Guidance Higher drywell activities for longer time MSIV leakage pathway more significant Lower containment activities Spray less effective CMT Leakage not as significant
Spray Effectiveness Longer Credit for higher effectiveness was a significant benefit
©2024 Nuclear Energy Institute 8 Current Licensing Basis Removal Mechanisms:
- Condenser credited for aerosol removal and holdup of MSIV leakage ECCS leakage pulled into RB and processed by Standby Gas Treatment MCR - Leakage from Condenser into Turbine Building (TB) and into MCR via unfiltered inleakage with no dispersion in Environment (MCR in TB)
For offsite doses - No credit for holdup in TB No other input changes were made to offset dose increases due to guidance changes Example 2: BWR-4, Mark-I LOCA Modeling
©2024 Nuclear Energy Institute 9 Example 2: BWR-4, Mark I LOCA Results
- CLB - Current Licensing Basis
- Rev. 1 - Rev. 1 RFs and timing; DW spray credit removed; MSL and Condenser removal aligned with A-5.6.1
- SAND2023 - SAND2023 RFs and timing; removal credits same as Rev. 1 case
- SAND2023_Scrub - SAND2023 case but release to DW airspace limited to SAND2023 Table 5-16 Excluding SP Inventory fractions (no DW spray)
©2024 Nuclear Energy Institute 10 Example 2: BWR/4, Mark I Containment - Conclusions
Impact of Higher RFs Substantial increase in dose significant nuclides (e.g., Iodines) drives doses up
Impact of More Conservative Aerosol Removal Modeling Inability to credit DW spray with the Rev. 1 MSL aerosol removal models leads to higher concentrations in DW as source for MSIV leakage Lower aerosol removal in Condenser leads to higher concentration leakage
Pool scrubbing is a large benefit based on SAND2023 showing most radionuclides are scrubbed by the Pool rather than released directly to the DW
©2024 Nuclear Energy Institute 11 Leakage Pathways:
Containment
ESF
RWST Backleakage Containment spray credited; terminated at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in CLB (or at decontamination factor cutoffs)
Spray duration modified to cover longer in-vessel release duration ESF leakage outside containment is filtered prior to release RWST back-leakage release included separate from ESF leakage Example 3: PWR, Large Dry Containment
©2024 Nuclear Energy Institute 12 Example 3: PWR, Large Dry Containment CLB - Current Licensing Basis Rev1_2hrSpray - Rev. 1 RFs and timing (2 hrs of cont. spray)
Rev1_ExtSpray - Cont. spray extended to cover in-vessel release SAND2023 - Use of RFs and timing from SAND2023 (2 hrs of cont. spray)
SAND2023_ExtSpray - Cont. spray extended to cover in-vessel release SAND23_HalRF - Halogen release capped at 100%
©2024 Nuclear Energy Institute 13 Sub-atmospheric containment depressurization profile is:
< 2.0 psig at 1.0 hr (after event initiation)
< 0.0 psig at 6.0 hr i.e., TS containment leakage rate of 0.1% vol/day from 0.0 to 1.0 hrs and 0.04% vol/day from 1.0 to 6.0 hrs ECCS Leakage outside containment is unfiltered prior to release 30,000 cc/hr total ECCS leakage with 10% flashing fraction RWST back-leakage release included separate from ESF leakage External shine contributions were not re-evaluated No other input changes were made to offset dose increases due to guidance changes Example 4: 3-Loop, PWR, Subatmospheric Containment
©2024 Nuclear Energy Institute 14 Example 4: 3-Loop, PWR, Subatmospheric Containment
- CLB - Current Licensing Basis
- Rev. 1 - Rev. 1 RFs and timing
- SAND2023 - Use of RFs and timing from SAND2023
- SAND2023_HalRF -Use of RFs and timing from SAND2023; Halogen release capped at 100%
©2024 Nuclear Energy Institute 15 PWR Conclusions
Timing Impacts Much longer in-vessel release durations for SAND2023 (and Rev. 1) can be beneficial If spray is credited, plants may need to extend spray duration to cover the longer in-vessel release duration
RF Impacts SAND2023 RFs drive doses higher than current RFs Could potentially result in reductions in operational flexibility (e.g., lower allowable ESF leakage)
Current guidance (separate leakage runs modeling all iodine release) results in total iodine releases above 1.0
©2024 Nuclear Energy Institute 16 Proposed Updates to RG 1.183 R1
©2024 Nuclear Energy Institute 17 NRC Supplemental Work (ML24005A089)
©2024 Nuclear Energy Institute 18 NRC Supplemental Work (ML24005A089)
©2024 Nuclear Energy Institute 19 Proposed Updates to RG 1.183 R1
Proposed approach: Rev. 2 would contain three (3) MHA LOCA RF tables containing separate Pool, Containment atmosphere, and Steam Line RFs instead of a single table (e.g., current Table 1)
How are the steam line release fractions identified in ML24005A089 intended to be applied in the downstream dose consequence codes?
Released over the course of the in-vessel release duration, fully released into the steam line source volume at the start of the in-vessel period, or something different altogether?
What is intended in guidance/application space with respect to the information in the red box (see previous slide) discussing potentially keeping concentration constant after the early in-vessel period?
©2024 Nuclear Energy Institute 20 Proposed Updates to RG 1.183 R1
MSL and Condenser Deposition RG 1.183, Rev. 1, presents 3 acceptable models for MSL / Condenser aerosol deposition NRC supplemental work has suggested RFs into MSLs directly based on MELCOR modeling that includes deposition between RPV and inboard MSIV Will the Rev. 1 MSL and Condenser deposition models apply downstream of the inboard MSIV or will updates be made to these models?
Natural Deposition in Containment Rev. 0 points to NUREG/CR-6189 (Powers) as an acceptable model (built into RADTRAD and used widely across the industry)
Rev. 1 states that NUREG/CR-6189 is no longer directly applicable without adjustment and provides no acceptable aerosol natural deposition model Given the information available in MELCOR modeling already performed, will an updated acceptable containment natural deposition model be provided in Rev. 2?
Alternatively, an acceptable method of adjusting the NUREG/CR-6189 correlations would be beneficial and avoid each licensee developing their own for Staff review
©2024 Nuclear Energy Institute 21 Proposed Updates to RG 1.183 R1
RF iodine releases greater than 1.0 Current wording from RG 1.183, Rev. 1, Appendix A:
©2024 Nuclear Energy Institute 22 Proposed Updates to RG 1.183 R1 Proposed wording for RG 1.183, Rev. 2:
Add to Position A-4.1: "...in the primary containment sump water (in PWRs) or suppression pool (in BWRs) at the time of release from the core. Given the release fractions in Tables 1 and 2, this guidance, combined with the guidance in A-2.1, would lead to release fractions of >1.0 being analyzed for certain nuclide groups. Licensees need not consider total releases that exceed 1.0 if justification is provided that the split between the containment airspace and the pool is conservative. In lieu of this deterministic approach..."
©2024 Nuclear Energy Institute 23 Questions/Comments/Discussions