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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 - 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[Table view] |
Text
FFIC US L PRED ION IN MA. N State-of-the-Art Reactor Consequence Analyses (SOARCA)
Semi-Annual Briefing for Commission Technical Assistants September 10, 2008 1
F IA SE NLýY- CIýSIONý FO ATýIONý ý
U I.
LY- P" CIýSI AL IýN AýTI -
Agenda
Project Status
- Plan to have the results of Peach Bottom
& Surry in Dec. 2008
- Peer-Review to follow in Jan. 2009 if approved
° Sequoyah analysis in progress F1 ALUSE Y-P ECISI N INFýoOON. 3
Project Status (cont)
SRM-SECY-08-0029
- Approval for dose and spatial truncation methodology (option 6)
- Approval for the external peer review
- Plan completed Revised Statement of Work
- Proposed external peer review
- Uncertainty Analysis
- Parameters have been identified, start date TBD
- Risk Communication ACRS comments
- Staff has taken steps or developed approach to address ACRS comments
" Full scope level 3 PRA
- Reporting health effects with LNT and a 5 Rem truncation value
- Plan to provide ACRS written documentation of SOARCA approach, methods, and results for Peach Bottom and Surry (details in next slides)
F1 US NLY EDEI ýNAI OMAT 4
ACRS Comments Full Scope level 3 PRA recommendation
- Staff's view that SOARCA approach is appropriate
" Consistent with objectives
" Proper focus on detailed realistic modeling
-Additional examination of SOARCA sequences
. Analysis of sequences with even lower frequency than 10-6 and 10.7 criteria
- Peach Bottom Short-Term Station Blackout Staff conclusions regarding lower frequency sequence demonstrated, by analysis, to be valid F ýA L 0 ýY - REE ECIS ýLI NF ýM ýTI 5
ACRS Comments (cont)
Seismic impact on EP
- Primary influence is on evacuation time estimate (ETE)
- Planned approach is to address by sensitivity analysis Potential LERF impact However, not expected for Peach Bottom and Surry
- Magnitude of release
- NA to Surry ISLOCA 6
Results
- Peach Bottom and Surry base cases (with B.5.b.
measures implemented)
- no early fatalities or latent cancer fatality risk (DBA-like release for Surry Short Term Station Blackout)
- Peach Bottom and Surry sensitivity cases (without B.5.b.
measures)
- no early fatalities; 10-4to 103 conditional individual latent cancer fatality risk 10-10 to 10-9 individual latent cancer fatality risk per sequence
° Staff believes this metriccould be used :for risk communication when the base case results in an environmental release
- Frames consequences in the context of a background risk and safety goals The 10 mrem dose truncation value has no significant impact on the average individual risk (option 6); reconsider ACRS' recommendation of LNT and 5 Rem truncation value F ýLýSEL PýýESIýN ýIýO ý 7
Peach Bottom - STSBO
- Frequency: 1 - 5x 10-7 R-Y
- New case - below SOARCA screening threshold; added to address potential LERF concerns below screening criteria
- Base case with B.5.b. measures implemented -
fission product release was prevented
- Sensitivity Case without B.5.b.measures (no Reactor Core Isolation Coolant System)
- Release begins at -8 hours,
- Radiological Release- 11% iodine, 2% cesium (t=48 hours)
- Not a LERF contributor C LUS N Y-PRONAF 8
Peach Bottom'- STSBO cont.
- no early fatalities Distance Interval Conditional Average Individual likelihood of a LCF (mi) LNT 10 mrem truncation 0-10 9.7x10- 4 0-50 1.6 x 10-4 1.5 x 10-4 1.0 x 0-&4 0-100 8.9 x 105 Reconsider LNT and 5 Rem truncation value?
\Oic ýL ONL -PRýEcISI ýAL ýINF MýA ON - 9
Peach Bottom Consequences CDF Early Conditional LNT - Individual Scenario per R-Y Fatalities Individual LCF risk per LCF risk sequence*
(0 -10 miles) (0 -10 miles)
Long Term Station ito 5 x 10-6 0 3 x 10-4 8 x 10-10 Blackout (LTSBO)
Short Term Station Blackout 1 to 5 x 10-7 0 1 x 10-3 3 x 10-10 Blackout (STSBO)
U.S. average individual risk of a cancer fatality: 2 x 10-3 /year 10
Surry Consequences Conditional LNT- Individual Scenario CDF Early Individual LOF risk per per R-Y Fatalities LCF risk sequence (0 -10 miles) (0 -10 miles)*
LTSBO 1 to 2 x 10-5 0 1 X 10-4 2 x 10-9 STSBO 1 to 2 x 10-6 0 6 x 10-4 8 x 10 -10 STSBO/3 to 5 x 10-7 0 9 x 10-4 4 x 10-10 TISGTR ISLOCAspar 3 x 10-8 0 2 X10- 3 6 x 10-11 ISLOCApra 7 x 10-7 0 2X10-3 1.x 10-9 U.S. average individual risk of a cancer fatality: 2 x 10-3 / year.
ISLOCA - Inter-systems loss of coolant accident 11 TISGTR - Thermally induced steam generator tube rupture
Surry ISLOCA
- Internally initiated event
- Sequence frequency
- Licensee's PRA- 7x10-7 /year
- SPAR - 3x1 0-8 / year (does not meet SOARCA screening criteria of lxl 07/ year)
- Base case Effectively mitigated - operators have sufficient time to switch to unaffected unit's refueling water storage tank (RWST) to prevent core damage
- Assumes operators fail to switch to unaffected unit's RWST
- Results in core damage and fission product release via the Safeguards Building QFIk LUS ýN-LYýP DE' 0 LI RýATIO0 12
Sensitivity Analysis
- Break elevation is uncertain
- NUREG-1 150 concluded that the probability of break being uncovered is 0.15 Sequence frequency
- Based on licensee's PRA - 6x10-7 /year (covered),
1x10-7 /year (uncovered)
- Based on SPAR - 3x1 0-8 / year (covered), 5x10-9 / year (uncovered)
- Preliminary results for sequence with break covered
- Release begins at-- 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
- Radiological Release - 9% iodine, 9% cesium Analysis ongoing for sequence with break uncovered L13
Release Magnitude (%)
12-10-6-
4 LII Iodine 2- I Cesium Sandia Siting Study (SSTI source term)
Iodine - 45%
Cesium - 67%
0FiI E 0O ýR ED SI N1ýAL Iý ORT1 TION 14
Updates / Insights
- Propose truncating fission product releases to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after start of release
- Generally consistent with NUREG-1 150
- Consistent with realistic consideration of anticipated EP measures and capabilities
- Airlift capability if access limited FCILU OLY- ED ISIO FO AON 15
SOARCA Insights
° Because fission product releases are delayed and substantially. smaller, offsite consequences are smaller than previously predicted o No early fatalities; No LERF Contributors
- Average individual latent cancer fatality risks are very low
- Most of the individual latent cancer risk is due to.
doses within the EPA Protective Action Guides and the assumed low dose healtheffects of the LNT dose response model OFFICIAL USE ONLY - PREDECISIONAL INFORMATION 16 1!1
i " , ,
WFF IýU S ý- RE I ýON A ýN OR ýTI SOARCA Insights (cont.)
e Risk to the public from long term exposure is extraordinarily small e Within the Emergency Planning Zone (EPZ)
For the BWR event (LTSBO) freq -3 x 10-6 / year Individual risk of a latent cancer fatality -3 x 10-4 conditional to occurrence of event (LNT assumption)
Absolute LCF risk to individual is -8 x 10-10 / year
- Risk is thousands of times smaller than the NRC safety goal
- Risk is millions of times smaller than all other cancer risks (2 x 10-3 / year)
- Risk outside the EPZ is smaller yet FICI SEQ PRED IS NALI ATI 17
/-
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