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| | number = ML18213A391 | | | number = ML18213A391 |
| | issue date = 07/12/2018 | | | issue date = 07/12/2018 |
| | title = 07/12/2018 Point Beach Nuclear Plant, Units 1 and 2 - Public Meeting | | | title = Public Meeting |
| | author name = | | | author name = |
| | author affiliation = NextEra Energy Point Beach, LLC | | | author affiliation = NextEra Energy Point Beach, LLC |
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| | docket = 05000266, 05000301 | | | docket = 05000266, 05000301 |
| | license number = DPR-024, DPR-027 | | | license number = DPR-024, DPR-027 |
| | contact person = Chawla M L, 415-8371 | | | contact person = Chawla M, 415-8371 |
| | document type = Meeting Briefing Package/Handouts | | | document type = Meeting Briefing Package/Handouts |
| | page count = 10 | | | page count = 10 |
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| =Text= | | =Text= |
| {{#Wiki_filter:CONSTRUCTION TRUSS License Amendment Request Point Beach Nuclear Plant Units 1 & | | {{#Wiki_filter:CONSTRUCTION TRUSS License Amendment Request Point Beach Nuclear Plant Units 1 & 2 Public Meeting July 12th 2018 |
| 2 Public Meeting July 12 th 2018 1 | |
| AGENDA *Introductions
| |
| *Purpose *Changes made since Nov 2017 audit
| |
| *Reviews performed
| |
| *Summary *Questions NextEra Personnel *Steve Catron Corporate Licensing
| |
| *Eric Schulz Point Beach Licensing
| |
| *Rich LaPlante Point Beach Engineering
| |
| *Ted Kulczycky Corporate PRA
| |
| *Anil Julka Corporate PRA
| |
|
| |
|
| PURPOSE *Provide overview of changes made to seismic and thermal hazard analysis.
| | 1 AGENDA |
| *Summarize results of independent review.
| | * Introductions |
| | * Purpose |
| | * Changes made since Nov 2017 audit |
| | * Reviews performed |
| | * Summary |
| | * Questions |
|
| |
|
| Changes Made Since the Audit In Nov 2017 CAFTA based event trees and fault trees used to assess seismic and thermal hazards. Integrated Internal Events Model into seismic and thermal hazard models.
| | NextEra Personnel |
| -Open findings addressed in Attachment A of PRA analysis.
| | * Steve Catron Corporate Licensing |
| Most dispositioned as no impact, conservative impact, or addressed with sensitivity analysis.
| | * Eric Schulz Point Beach Licensing |
| Seismic fragilities from IPEEE.
| | * Rich LaPlante Point Beach Engineering |
| -Some IPEEE fragilities updated. Addressed modifications made to the plant post IPEEE based on IPEEE insights. | | * Ted Kulczycky Corporate PRA |
| Commitment to modification that will fully protect U2 PORV control cables from missile hazards
| | * Anil Julka Corporate PRA |
| - spring 2020.
| |
| HEPs based on latest EPRI methodology.
| |
| Quantified LERF based on bounding or conservative qualitative and quantitative assumptions related to containment integrity post construction truss failure.
| |
| Comprehensive sensitivity studies address key uncertainties. Followed guidance in RG 1.174 and NUREG 1855.
| |
|
| |
|
| Summary of third party review Review Scope Overall methodology and results Bounding Analysis Demonstrably Conservative Analysis HRA Conformance to RG 1.174; defense in depth, safety margin, and risk acceptance guidelines. | | PURPOSE |
| Conformance to RG 1.200 | | * Provide overview of changes made to seismic and thermal hazard analysis. |
| - high level review. Reasonableness of assumptions and inputs. | | * Summarize results of independent review. |
| | |
| | Changes Made Since the Audit In Nov 2017 |
| | * CAFTA based event trees and fault trees used to assess seismic and thermal hazards. |
| | * Integrated Internal Events Model into seismic and thermal hazard models. |
| | - Open findings addressed in Attachment A of PRA analysis. Most dispositioned as no impact, conservative impact, or addressed with sensitivity analysis. |
| | * Seismic fragilities from IPEEE. |
| | - Some IPEEE fragilities updated. Addressed modifications made to the plant post IPEEE based on IPEEE insights. |
| | * Commitment to modification that will fully protect U2 PORV control cables from missile hazards - spring 2020. |
| | * HEPs based on latest EPRI methodology. |
| | * Quantified LERF based on bounding or conservative qualitative and quantitative assumptions related to containment integrity post construction truss failure. |
| | * Comprehensive sensitivity studies address key uncertainties. Followed guidance in RG 1.174 and NUREG 1855. |
| | |
| | INDEPENDENT REVIEW Summary of third party review Review Scope Key Comments Overall methodology and results Innovative approach supported with good Bounding Analysis arguments that justify methodology. |
| | Demonstrably Conservative Analysis Confirmed key issues addressed appropriately. |
| | HRA Editorial comments helped clarify methodology Conformance to RG 1.174; defense in depth, for reviewers. |
| | safety margin, and risk acceptance Validated assumptions were reasonable and well guidelines. supported. |
| | Conformance to RG 1.200 - high level Recommended additional sensitivity analyses to review. address key uncertainties associated with Reasonableness of assumptions and inputs. quantitative and qualitative inputs and assumptions. |
| Appropriate integration of structural inputs. | | Appropriate integration of structural inputs. |
| Appropriate integration of internal events model and Seismic IPEEE. | | Supporting HRA documentation enhanced in Appropriate integration of internal events conjunction with limited quantification revision model and Seismic IPEEE. |
| Uncertainty Conformance to NUREG 1855 guidance Confirm sensitivity studies address key uncertainties. | | No changes required to model structure Uncertainty Conformance to NUREG 1855 guidance Clarifications made on seismic/structural inputs Confirm sensitivity studies address key ALL COMMENTS INCORPORATED OR RESOLVED. |
| Key Comments Innovative approach supported with good arguments that justify methodology.
| | uncertainties. |
| Confirmed key issues addressed appropriately.
| | 6 |
| Editorial comments helped clarify methodology for reviewers.
| | |
| Validated assumptions were reasonable and well supported.
| | RESULTS Point Beach ALL HAZARDS PRA Results HAZARD CDF (1/Rx Yr) LERF (1/Rx Yr) |
| Recommended additional sensitivity analyses to address key uncertainties associated with quantitative and qualitative inputs and assumptions.
| | Unit 1 Unit 2 Unit 1 Unit 2 TOTAL 7.2E-05 8.2E-05 2.3E-06 2.5E-06 Case CDF LERF Bounding 1.93E-06 7.55E-07 Demonstrably Conservative 2.19E-07 5.26E-08 NRC RG 1.174 FIGURE 4 NRC RG 1.174 FIGURE 5 TOTAL CDF - ALL HAZARDS TOTAL LERF - ALL HAZARDS |
| Supporting HRA documentation enhanced in conjunction with limited quantification revision No changes required to model structure Clarifications made on seismic/structural inputs ALL COMMENTS INCORPORATED OR RESOLVED.
| |
| 6 INDEPENDENT REVIEW
| |
|
| |
|
| Point Beach ALL HAZARDS PRA Results HAZARD CDF (1/Rx Yr)
| | CONCLUSION |
| LERF (1/Rx Yr)
| | * Low risk impact |
| Unit 1 Unit 2 Unit 1 Unit 2 TOTAL 7.2E-05 8.2E-05 2.3E-06 2.5E-06 RESULTS NRC RG 1.174 FIGURE 4 TOTAL CDF
| | * PRA Identified mods that will protect critical mitigating functions during seismic and thermal events. |
| - ALL HAZARDS NRC RG 1.174 FIGURE 5 TOTAL LERF
| | * Supporting evaluations based on bounding and conservative assumptions |
| - ALL HAZARDS Case CDF LERF Bounding 1.93 E-06 7.55 E-07 Demonstrably Conservative 2.19 E-07 5.26 E-08 CONCLUSION Low risk impact PRA Identified mods that will protect critical mitigating functions during seismic and thermal events.
| | * Meets RG 1.174 requirements |
| Supporting evaluations based on bounding and conservative assumptions Meets RG 1.174 requirements | | - PRA quality meets RG 1.200 |
| -PRA quality meets RG 1.200
| | - Open F&O impacts will be addressed |
| -Open F&O impacts will be addressed Independent reviews from industry experts confirmed validity of methodology and assumptions.
| | * Independent reviews from industry experts confirmed validity of methodology and assumptions. |
|
| |
|
| QUESTIONS *Questions}} | | QUESTIONS |
| | * Questions}} |
Letter Sequence Request |
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MONTHYEARNRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances2017-03-31031 March 2017 License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances Project stage: Request ML17202G5912017-07-25025 July 2017 Audit Plan and Setup of Online Reference Portal for License Amendment Request - Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances Project stage: Other NRC 2017-0039, Construction Truss License Amendment Request Audit Plan2017-08-10010 August 2017 Construction Truss License Amendment Request Audit Plan Project stage: Request ML17307A0402017-10-30030 October 2017 E-mail Draft Request for Additional Information for Containment Dome Truss LAR - Point Beach Nuclear Plant, Units 1 and 2 (CAC Nos. MF9532 and MF9533; EPID L-2017-LLA-0209) Project stage: Draft RAI ML17319A2272017-11-17017 November 2017 Audit Plan for License Amendment Request to Resolve Non-Conformances Relating to Containment Dome Truss Project stage: Other ML17346A9122017-12-22022 December 2017 Summary of November 14, 2017 Public Teleconference with NextEra Energy Point Beach, LLC, to Discuss Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (CAC Nos. MF9532 and MF9533; EPID L-2017-L Project stage: Meeting ML18025C0432018-01-31031 January 2018 Request for Additional Information Regarding License Amendment Request to Resolve Nonconformances Relating to Containment Dome Truss Project stage: RAI ML18038A7852018-03-0606 March 2018 Summary Report for NRC Audit for Point Beach Nuclear Plant, Units 1 and 2, License Amendment Request to Resolve Nonconformance Relating to Containment Dome Truss Project stage: Other NRC 2018-0014, NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information2018-04-12012 April 2018 NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information Project stage: Response to RAI NRC 2018-0001, Transmittal of Construction Truss License Amendment Request Document2018-04-12012 April 2018 Transmittal of Construction Truss License Amendment Request Document Project stage: Request NRC 2018-0030, Construction Truss License Amendment Request 278 Draft Updated Final Safety Analysis Report (UFSAR) Revision2018-05-29029 May 2018 Construction Truss License Amendment Request 278 Draft Updated Final Safety Analysis Report (UFSAR) Revision Project stage: Draft Request ML18179A4032018-06-29029 June 2018 Public Meeting Discussion Points Project stage: Meeting ML18213A3912018-07-12012 July 2018 Public Meeting Project stage: Request ML18214A1532018-08-0101 August 2018 NRR E-mail Capture - Final - Second Round RAIs - Point Beach Nuclear Plant, Units 1 and 2 - License Amendment Request to Resolve Non-conformances Relating to Containment Dome Truss - EPID L-2017-LLA-0209 Project stage: RAI ML18220B0192018-08-13013 August 2018 7/12/2018 Summary of Meeting with NextEra Energy Point Beach, Llc. to Discuss Supplemental Response to the RAI for Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit 1 and 2 (CAC Nos. MF9532 & MF9533; ... Project stage: RAI NRC 2019-0007, License Conditions and Implementation Items Required to Resolve Construction Truss Design Code Nonconformances2019-03-13013 March 2019 License Conditions and Implementation Items Required to Resolve Construction Truss Design Code Nonconformances Project stage: Request ML18345A1102019-03-26026 March 2019 Redacted Version, Issuance of Amendment Nos. 263 and 266 for Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances Project stage: Approval 2018-03-06
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24227A5692024-08-31031 August 2024 NextEra - Pre-Application 10 CFR 50.69 8/28/2024 Meeting Slides ML24240A1502024-07-15015 July 2024 End-of-Cycle Public Outreach Meeting Presentation ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML22181B0842022-06-30030 June 2022 2021 Point Beach Nuclear Plant End-of-Cycle Meeting Handout ML21336A7972021-12-0909 December 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC - December 9, 2021 (Slides) ML21335A0232021-12-0808 December 2021 Slides - Point Beach Nuclear Plant, Unit Nos. 1 and 2 December 8, 2021 Public Meeting Slides for the Draft Plant-Specific Supplement 23, Second Renewal Dseis Public Meeting ML21285A1212021-08-0505 August 2021 SLRA Public Meeting Discussion Questions August 5 2021 ML21162A2632021-06-11011 June 2021 2020 Point Beach Nuclear Plant End-of-Cycle Meeting Presentation ML21134A0232021-05-18018 May 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC (NextEra) ML21042B9452021-02-17017 February 2021 Scoping and Process Meeting - February 17, 2021 ML20240A2702020-08-27027 August 2020 2019 EOC Slide Presentation ML18213A3912018-07-12012 July 2018 Public Meeting ML18179A4032018-06-29029 June 2018 Public Meeting Discussion Points ML18108A0152018-05-0101 May 2018 NextEra Approach to Resolution of Tornado Missile Protection May 1, 2018 ML18121A3392018-05-0101 May 2018 Slides for Point Beach 2017 EOC Open House ML17023A0652017-01-24024 January 2017 Pre-Submittal Call Regarding License Amendment Requests for Prairie Island Nuclear Generating Plant, Units 1 and 2 and Monticello Nuclear Generating Plant Emergency Action Level Scheme Changes ML16291A1772016-10-18018 October 2016 License Amendment Request Pre-Submittal Discussion October 18, 2016 ML16154A6772016-05-25025 May 2016 Annual Assessment Meeting/Open House (Hand Out) ML15112A0672015-04-20020 April 2015 Annual Assessment Meeting Open House - Handout EOC 2014 Mtg ML15091A5172015-04-0606 April 2015 4/6/2015, Meeting Slide for Public Teleconference on Point Beach MCR Abandonment Analysis for Loss of Control Scenarios ML14112A4252014-04-0808 April 2014 Annual Assessment Meeting, 2013 Reactor Oversight Process - Slides ML13162A7902013-06-11011 June 2013 Meeting Slides ML12206A3252012-08-0707 August 2012 G20120513/EDATS: OEDO-2012-0436 - Briefing Book for Meeting with Duke Energy on August 7, 2012 ML1114603332011-05-25025 May 2011 EOC Licensee Presentation Slides ML1107703492011-03-22022 March 2011 3/22/11 PRE-Application Meeting Slides Regarding NFPA 805 License Amendment Request ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1011304452010-04-22022 April 2010 FPL Energy Point Beach Handout from End-Of-Cycle Public Meeting ML0921107842009-07-29029 July 2009 Meeting Slides, Public Meeting with NRC Region III on Point Beach ML0912007212009-04-29029 April 2009 NRC Presentation Handouts for Point Beach 2008 End-of-Cycle Public Meeting ML0912007042009-04-29029 April 2009 Presentation at 2008 End-of-Cycle Public Meeting ML0912007342009-04-29029 April 2009 NRC Slides for Point Beach 2008 End-of-Cycle Public Meeting ML0828905272008-10-14014 October 2008 Meeting with NRC on AST ML0822503302008-10-0606 October 2008 Teleconference Summary Regarding Point Beach Nuclear Plant Supplement to the Auxiliary Feedeater Amendment ML0826819412008-09-24024 September 2008 Meeting Slides, FPL Energy Point Beach Public Meeting with NRC Region III ML0825401402008-09-16016 September 2008 Meeting Slides Point Beach Nuclear Plant Meeting with NRC on Epu. ML0819905262008-07-16016 July 2008 EOC Annual Assessment Meeting Slides ML0705106742007-02-21021 February 2007 NMC Slides for Public Meeting, Conduct of Operations Action Plan Update. ML0632601422006-11-21021 November 2006 11/21/2006 Informational Meeting Regarding Prairie Island License Renewal Application ML0604406422006-02-10010 February 2006 Summary of Public Meeting to Discuss Point Beach Self-Assessments, Summary Letter & Licensee Slides ML0434900602004-11-30030 November 2004 NMC Slides for 11/30/04 Public Meeting ML0413803782004-05-0707 May 2004 NMC New Fuel Supplier Development Initiative ML0412602942004-04-21021 April 2004 Public Meeting Slides, Point Beach 2003 End-of-Cycle Assessment ML0511502282004-04-19019 April 2004 Public Meeting Slides Point Beach EOC Performance Assessment ML0336406072004-01-0505 January 2004 Summary of Meeting with Nuclear Management Company, LLC Potential Repairs That May Overlap Remnant j-groove Welds on the Upper Reactor Vessel Head Penetrations ML0316902142003-06-16016 June 2003 Enclosure 1- NMC Handout Regulatory Conference Concerning Auxiliary Feedwater Orifice Issue for 06/06/2003 Point Beach Regulatory Conference ML0316903022003-06-16016 June 2003 Enclosure 3b - NMC Handout Regu;Atory Conference Concerning Auxiliary Feedwater Orifice Issue for 06/06/2003 Point Beach Regulatory Conference NRC 2003-0056, Submittal of the Auxiliary Feedwater Orifice Issue Regulatory Conference Slide Presentation2003-06-10010 June 2003 Submittal of the Auxiliary Feedwater Orifice Issue Regulatory Conference Slide Presentation ML1122206032003-06-0606 June 2003 Meeting Presentation, Point Beach, Regulatory Conference, EA-03-057 ML0312202182003-04-25025 April 2003 Public Meeting, Point Beach Re EOC, Licensee'S Slides ML0309300732003-04-25025 April 2003 Public Meeting, Point Beach Re EOC, Slides 2024-08-31
[Table view] |
Text
CONSTRUCTION TRUSS License Amendment Request Point Beach Nuclear Plant Units 1 & 2 Public Meeting July 12th 2018
1 AGENDA
- Changes made since Nov 2017 audit
NextEra Personnel
- Steve Catron Corporate Licensing
- Eric Schulz Point Beach Licensing
- Rich LaPlante Point Beach Engineering
- Ted Kulczycky Corporate PRA
PURPOSE
- Provide overview of changes made to seismic and thermal hazard analysis.
- Summarize results of independent review.
Changes Made Since the Audit In Nov 2017
- CAFTA based event trees and fault trees used to assess seismic and thermal hazards.
- Integrated Internal Events Model into seismic and thermal hazard models.
- Open findings addressed in Attachment A of PRA analysis. Most dispositioned as no impact, conservative impact, or addressed with sensitivity analysis.
- Seismic fragilities from IPEEE.
- Some IPEEE fragilities updated. Addressed modifications made to the plant post IPEEE based on IPEEE insights.
- Commitment to modification that will fully protect U2 PORV control cables from missile hazards - spring 2020.
- Quantified LERF based on bounding or conservative qualitative and quantitative assumptions related to containment integrity post construction truss failure.
- Comprehensive sensitivity studies address key uncertainties. Followed guidance in RG 1.174 and NUREG 1855.
INDEPENDENT REVIEW Summary of third party review Review Scope Key Comments Overall methodology and results Innovative approach supported with good Bounding Analysis arguments that justify methodology.
Demonstrably Conservative Analysis Confirmed key issues addressed appropriately.
HRA Editorial comments helped clarify methodology Conformance to RG 1.174; defense in depth, for reviewers.
safety margin, and risk acceptance Validated assumptions were reasonable and well guidelines. supported.
Conformance to RG 1.200 - high level Recommended additional sensitivity analyses to review. address key uncertainties associated with Reasonableness of assumptions and inputs. quantitative and qualitative inputs and assumptions.
Appropriate integration of structural inputs.
Supporting HRA documentation enhanced in Appropriate integration of internal events conjunction with limited quantification revision model and Seismic IPEEE.
No changes required to model structure Uncertainty Conformance to NUREG 1855 guidance Clarifications made on seismic/structural inputs Confirm sensitivity studies address key ALL COMMENTS INCORPORATED OR RESOLVED.
uncertainties.
6
RESULTS Point Beach ALL HAZARDS PRA Results HAZARD CDF (1/Rx Yr) LERF (1/Rx Yr)
Unit 1 Unit 2 Unit 1 Unit 2 TOTAL 7.2E-05 8.2E-05 2.3E-06 2.5E-06 Case CDF LERF Bounding 1.93E-06 7.55E-07 Demonstrably Conservative 2.19E-07 5.26E-08 NRC RG 1.174 FIGURE 4 NRC RG 1.174 FIGURE 5 TOTAL CDF - ALL HAZARDS TOTAL LERF - ALL HAZARDS
CONCLUSION
- PRA Identified mods that will protect critical mitigating functions during seismic and thermal events.
- Supporting evaluations based on bounding and conservative assumptions
- PRA quality meets RG 1.200
- Open F&O impacts will be addressed
- Independent reviews from industry experts confirmed validity of methodology and assumptions.
QUESTIONS