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Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23338A1522023-12-0707 December 2023 Public Meeting Slides for North Anna and Surry Emergency Plan Augmentation Times License Amendment Request ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23251A0782023-09-0606 September 2023 DRE1 Decom Pre-Submittal Slides ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23103A3482023-04-14014 April 2023 Annual Assessment Meeting Presentation for North Anna and Surry ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22097A2262022-04-13013 April 2022 Presubmittal Presentation April 13, 2022 One-time TS Change of AOT for Unit 2 AFW Piping Replacement ML22091A0902022-04-0101 April 2022 Combined 2021 Assessment Meeting Slides ML22055B1132022-03-0202 March 2022 Technical Support Center (TSC) Relocation Proposed License Amendment Request - NRC Pre-Submittal Meeting, March 2, 2022 ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21134A1632021-05-20020 May 2021 Resolution of Tornado Wind Nonconformances Proposed License Amendment Request NRC Pre-Submittal Meeting - May 20, 2021 ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request ML21034A5972021-02-10010 February 2021 External Presentation Am Atkinson_Nrc ISG-06 Meeting Dominion Digital IC Project 02102021 ML20307A1772020-11-0404 November 2020 NRC Presentation North Anna Power Station, Units 1 and 2 Subsequent License Renewal Review ML20309A5912020-10-14014 October 2020 Pre-Submittal Meeting for License Amendment Requests to Implement Batch Framatome 15 X 15 AGORA-5A-I (Agora) Fuel at Surry Power Station Units 1 and 2 (SPS) - Slides ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20098B6022020-04-0707 April 2020 Annual Assessment Meeting Presentation ML20098B7292020-04-0707 April 2020 Sur 2019 Annual Assessment Meeting Presentation ML19311C5292019-11-0707 November 2019 Dsies Slides for Nov. 7, 2019 Public Meeting ML19296D7862019-11-0606 November 2019 Dseis Slides for November 7, 2019 Public Meeting ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19248C7352019-09-0909 September 2019 CFR 50.69 License Amendment Request Pre-Submittal Meeting with NRC - September 9, 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML19007A2162019-01-0808 January 2019 Subsequent License Renewal Environmental Scoping Meeting, Surry Power Station, Unit Nos. 1 and 2, January 8, 2018 ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18275A3712018-09-25025 September 2018 Subsequent License Renewal Environmental Scoping Meeting 9-25-18 ML18141A3072018-05-21021 May 2018 18 - SLR Status ML18102A5692018-04-17017 April 2018 Dominion'S Presentation on Surry'S SLRA Safety Meeting-Final (for April 17, 2018) ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML18032A5842018-02-0707 February 2018 SLR Pre-Application 02/07/2018 Meeting - Dominion Energy Slides 2024-01-30
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23338A1522023-12-0707 December 2023 Public Meeting Slides for North Anna and Surry Emergency Plan Augmentation Times License Amendment Request ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23103A3482023-04-14014 April 2023 Annual Assessment Meeting Presentation for North Anna and Surry ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session ML22097A2262022-04-13013 April 2022 Presubmittal Presentation April 13, 2022 One-time TS Change of AOT for Unit 2 AFW Piping Replacement ML22055B1132022-03-0202 March 2022 Technical Support Center (TSC) Relocation Proposed License Amendment Request - NRC Pre-Submittal Meeting, March 2, 2022 ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21134A1632021-05-20020 May 2021 Resolution of Tornado Wind Nonconformances Proposed License Amendment Request NRC Pre-Submittal Meeting - May 20, 2021 ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request ML21095A0162021-04-0505 April 2021 2021 RIC Session T12 - DOE-Sponsored Light Water Reactor Sustainability Program ML21034A5972021-02-10010 February 2021 External Presentation Am Atkinson_Nrc ISG-06 Meeting Dominion Digital IC Project 02102021 ML20307A1772020-11-0404 November 2020 NRC Presentation North Anna Power Station, Units 1 and 2 Subsequent License Renewal Review ML20309A5912020-10-14014 October 2020 Pre-Submittal Meeting for License Amendment Requests to Implement Batch Framatome 15 X 15 AGORA-5A-I (Agora) Fuel at Surry Power Station Units 1 and 2 (SPS) - Slides ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20098B6022020-04-0707 April 2020 Annual Assessment Meeting Presentation ML20098B7292020-04-0707 April 2020 Sur 2019 Annual Assessment Meeting Presentation ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19311C5292019-11-0707 November 2019 Dsies Slides for Nov. 7, 2019 Public Meeting ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19084A0982019-03-22022 March 2019 Potential Topics for Pre-Application Meetings for Peach Bottom SLRA ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML19007A2162019-01-0808 January 2019 Subsequent License Renewal Environmental Scoping Meeting, Surry Power Station, Unit Nos. 1 and 2, January 8, 2018 ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18320A2502018-11-20020 November 2018 50.90 License Amendment Request - Dominion Fleet EAL Scheme Changes, November 20, 2018 Public Meeting ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18144A6932018-05-31031 May 2018 License Amendment Request for Expanded Actions for LEFM Flow Meter Conditions - NRC Pre-Submittal Meeting May 31, 2018 ML18141A3072018-05-21021 May 2018 18 - SLR Status ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML18032A5842018-02-0707 February 2018 SLR Pre-Application 02/07/2018 Meeting - Dominion Energy Slides ML17320A2012017-11-15015 November 2017 Modeling FLEX in Surry Power Station Internal Events and Flooding PRA 2024-01-30
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US.NRC U
UNITED STATES NUCLEAR REGULATORY COMMISSION ProtectingPeople and the Environment State-of-the-Art Reactor Consequence Analyses (SOARCA)
Semi-Annual Briefing for Commission TAs August 13, 2009 OF 9 AL ýSE ýN ý-S ýIT I INT ýAý N FO ýA ION
Presentation Outline
" Status of Project
° Peer Review
" Upcoming Dates
" Communications Activities 9 Seismic (EP) Study OF AL ONLY - NSIT ER LIN M ION 2 N
Status of Project
- Accomplishments since last TA briefing (4/17/2009)
- Seismic (EP) study for Peach Bottom and Surry
- Draft NUREG
- SRA Webinar Held 7/20/2009
- First Peer Review Committee Meeting Challenges
- Aggressive schedule to meet WITS Due Dates
- Staff continuity and available expertise e Sequoyah analysis is on hold
- Differing technical views remain "Fl L6S ONL- -SE ýSITýIVE ýT ýNAL I OR ýTIOýý 3
Review of Draft ExecutiveSummary Differing technical views were not considered in the Executive Summary included with SECY-09-0045
- Met with staff to review comments
- Revised Executive Summary provided to Peer Review Committee July 2nd
- Draft provided to DEDMRT and management steering committee
- Work continues on revisions
- Engaging Peer Review Committee with subset of issues 0 l LSOL-F TVILNO T - 4
Management Steering Committee
- Met with steering committee July 2 2 nd
- Provided revised draft Executive Summary
- Summarized and discussed comments
- Steering committee suggested engaging the Peer Review committee
- Members to provide suggestions on which issues to provide for Peer Review
- May add Regional Representation FFI S ONLY NSITIV N 5
Peer Review
" Chair
- Karen Vierow (Associate Professor, Nuclear Engineering, Texas A&M)
" PRA Sequence Selection & Mitigative Measures
- Bruce Mrowca (ISL)
- Ken Canavan (EPRI)
- Accident Progression and Radiological Release
- Bernard Clement (IRSN)
- Robert Henry (Fauske and Associates)
- Jeff Gabor (ERIN Engineering)
- Offsite Radiological Consequences
- Kevin O'Kula (Washington Safety Management Solutions LLC URS Corporation -
Washington Division)
- Dave Leaver (WorleyParsons Polestar)
- Roger Kowieski (Natural and Technological Hazards Management Consulting, Inc.)
- Structural-Failure (Seismic) Expert
- John Stevenson (JD Stevenson Consulting Engineer)
- Jacquelyn Yanch (Professor, Nuclear Engineering, MIT)
OFI AL S NL-S SVE ITE N I R 0 6
Peer Review Charter
- Requesting individual input
- Non-FACA committee - no consensus sought
- Seeking review to "...insure that the study is best estimate and technically sound."
- Specifically requesting review of the robustness of conclusions and Executive Summary FFCI LU LY - SITI TERA7
Preliminary Summary of Peer Review Comments 72 comments received August 7th
- Currently reviewing and prioritizing Summary of Comments
- Plans for uncertainty study
- not all members commented on the issue
- Committee "seemed" OK publishing without the uncertainty study
" interested in our parameters and their ranges
- Committee discussed the robustness of the MELCOR calculations
- focused on equipment performance and structural failure modeling
" requested sensitivity studies
- The probability of the success of mitigation
" can operators perform the functions?
- are mitigative measures included in current plant procedures?
- justification for our assumptions
- how to discuss the mitigated vs. unmitigated results in the Executive study.
8
Upcoming Dates
- 09/15-16/09 (scheduled)
- 11/10-11/09 (tentative)
- estimated completion date April 2010
- planning to request peer review input and feedback
- OECD/NEA workshop on Implementation of Severe Accident Management Measures, October 2009
- Subcommittee Meeting 11/4/09
- Full Committee Meeting 11/5/09
- Final NUREG Including Peer Review and Recommendation Regarding Future Work
- to SECY 1/29/10 FF0 US 9Y- N TIVEI ALJ M I9
m F icaLnSE Y-E ITI T AL FOMpTI Communications Accomplishments i SOARCA public website updated to reflect Communication Plan provided to Commission in SECY-09-0045.
- NRC Reporter and The Researcherarticles published for staff communication
- OPA Briefed NEI Communications Staff on SOARCA
° Revised Communications Plan to Recognize the Need to Brief our Federal Partners such as FEMA, EPA, etc.
10
Seismic (EP) Study
- Background - ACRS questioned adequacy of EP modeling (for seismically initiated SOARCA scenarios) which did not explicitly consider effect of seismic event on EP
- Past risk studies have not generally considered this effect except as simplified sensitivity calcs (delay times and evac speed)
- Seismic assessment of infrastructure by RES seismic experts
, Bridges, roads, power network (notification, traffic signals)
- Reassessment of EP given impact on infrastructure and ORO's
- Route alerting assessment by SNL/NSIR staff
- New ETE assessment based on available road network
- New EP model developed for MACCS2
- Recalculation of offsite consequences
- Conclusion - No substantial effect on offsite health consequences OAF I ALU 0LY-NTRN I EQ M TI11
Seismic (EP) Study Peach Bottom - Unmitigated Short-Term SBO Assuming LNT M Baseline EP U Seismic EP 8.0E-11 ~1 6.OE-11 4 --
.X CL 4)
It U. 4.OE-11 +/--
-C V
2.OE O.OE+00 4-0-10 0-50 0-100 Distance (miles)
FF1 L L-s S0 I A E ATI 12
Seismic (EP) Study Surry - Unmitigated Thermally Induced Steam Generator Tube Rupture Assuming LNT l[Baseline EP N Seismic EP 2.OE-10 1.5E LL 1.OE-10 --
C 5.OE-11 -I---
0.OE+00 4--
0-10 0-50 0-100 Distance (miles)
ýNA ýI INT_ R ýON 13
!SSEOý L -S ý"IT I
'Seismic (EP) Study
- Seismic effects of EP are site specific but with no substantial effect on health consequences
- Peach Bottom
" Sirens fail but alternative notification is adequate, larger shadow evacuation
" Free span bridges fail - but they are not key to evacuation, adequate road network remains and evacuation speeds are unchanged
" In addition, sequence timing predicted by realistic analysis is delayed so that there is some "margin" for EP activation and execution 14
ebismic (EP) Study USE cST LY-iE T L IStud 15
ýsoý "ý
Seismic (EP) Study Surry
" Sirens function, public evacuation starts earlier, shadow evac occurs, schools delayed
" Bridge failures significantly retard evacuation -
major effect on evacuation speed
- Smaller radiological release, LCF dominated by long term 16
Seismic (EP) Study I '- W7oro C.
0 "
V R G I A fN I 0.p.rtNewi 00, FO AN 17
Conclusions
- SOARCA represents major change from the way people perceive severe reactor accidents and their likelihood and consequences
- Mitigation is likely (due to time and redundancy) and, when it is implemented, effective in preventing core damage
- Impact on existing level 1 PRA Unmitigated accidents progress more slowly with smaller releases, no LERF
- Impact on existing level 2 PRA Early fatality risk lower than previous studies Dominance .of external-events suggests need for corresponding PRA focus o Seismic research needed:`
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