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| {{#Wiki_filter:}} | | {{#Wiki_filter:Point Beach GL 2004-02 Resolution Update NextEra Energy Point Beach, LLC (NextEra) |
| | December 9, 2021 |
| | |
| | Meeting Agenda |
| | * Overview of Plant Layout and Strainer Configuration |
| | * Overview of Risk-Informed Resolution Approach |
| | * Risk and Uncertainty Quantification |
| | * Content of Submittal |
| | * Current Status and Submittal Schedule Meeting Objectives |
| | * Communicate current status of PBN response to GL 2004-02 |
| | * Obtain staff feedback on the overall risk-informed resolution path 2 |
| | |
| | PBN Plant Layout |
| | * Westinghouse 2-loop pressurized water reactor (PWR) with large dry containment |
| | * Two redundant emergency core cooling system (ECCS) and containment spray (CS) trains |
| | - Each train has a high-head safety injection (SI) pump, residual heat removal (RHR) pump, and CS pump |
| | - During recirculation, the CS and SI pumps take suction from the RHR pump discharge 3 |
| | |
| | Sump Strainer Arrangement Unit 1 Unit 2 |
| | * PCI Sure-Flow strainers |
| | * Vertical disk modules around a core tube |
| | * Surface area of 1904.6 ft2 per train 4 |
| | |
| | ===Background=== |
| | * Previous GL Response submitted to the NRC in 2017 (ML17363A253) |
| | * NRC performed an audit of the submittal in January 2019 and issued an audit report in December 2019 with several questions |
| | * PBN was able to address all questions from the audit report except for Mineral Wool cassettes having a lower destruction pressure than assumed |
| | * NextEra conducted an alternative analysis for PBN to determine the best path for closeout of GL 2004-02 |
| | * The selected option was the use of a risk-informed resolution approach 5 |
| | |
| | Overview of Risk-Informed Approach |
| | * PBNs risk-informed approach is similar to Vogtle |
| | * Overall evaluation based on models that have been used in the past and accepted by the NRC for GSl-191 resolution |
| | * Screening of break scenarios and high likelihood equipment configurations |
| | * Multiple breaks postulated at each Class 1 weld within first isolation valve on primary loop |
| | * NARWHAL software evaluated each primary side break to determine if it would result in strainer failures due to effects of debris |
| | * In-vessel downstream effects analyzed in a bounding evaluation outside of NARWHAL 6 |
| | |
| | Overview of Risk-Informed Approach |
| | * Conditional failure probabilities (CFPs) calculated for each equipment lineup and PRA break size category |
| | * Change in core damage frequency (CDF) calculated outside PRA model using LOCA frequencies and equipment failure probabilities |
| | * Change in large early release frequency (LERF) calculated from conditional large early release probability for a large LOCA given core damage |
| | * Risk contribution of secondary side breaks evaluated conservatively assuming all breaks fail the strainers due to effects of debris |
| | * The total CDF and LERF values are obtained from the PBN PRA model |
| | * Risk quantification results compared with RG 1.174 acceptance guidelines 7 |
| | |
| | PBN Risk-Informed Approach 8 |
| | |
| | Revision to Debris Generation Calculations |
| | * ZOI size for mineral wool increased to 5.4D |
| | * Mineral wool insulation is similar to K-Wool, which is classified as unjacketed mineral wool with wire mesh reinforcement in NEI 04-07 |
| | * K-Wool went through air jet impact testing and was assigned a ZOI size of 5.4D per NEI 04-07 SE |
| | - Tested K-Wool had wire mesh lining and fabric cover |
| | * Mineral wool insulation at PBN is encapsulated in stainless steel cassettes |
| | * All mineral wool within the 5.4D ZOI is assumed to be fines |
| | - Shown to be more conservative than using 17D ZOI and LDFG size distribution |
| | * This assumption is similar to that used by Surry and North Anna 9 |
| | |
| | Acceptance Criteria for Risk Quantification |
| | * NARWHAL software used to evaluate strainer performance |
| | - Strainer head loss vs. pump NPSH margin and strainer structural margin NPSHr adjusted for degasification using RG 1.82 methodology |
| | - Gas voids from degasification or flashing compared with acceptance limits |
| | - Debris loads of a break compared with debris limits |
| | - Head loss compared with acceptance criterion for partially submerged strainer |
| | * Bounding analyses were performed for the following acceptance criteria |
| | - Upstream blockage does not prevent water from reaching sump |
| | - Pump performance not affected by air intrusion from vortexing |
| | - Penetrated debris within ex-vessel wear and blockage limits |
| | - In-vessel fiber load within WCAP-17788 limit for Westinghouse two-loop plant 10 |
| | |
| | Evaluation of In-Vessel Downstream Effects |
| | * In-vessel downstream effects was analyzed outside of NARWHAL following latest NRC review guidance |
| | * Determined total in-vessel fiber load for the bounding hot leg break using WCAP-17788 methodology |
| | * Maximum total in-vessel fiber load is ~85 g/FA, which is less than the limit in WCAP-17788 for Westinghouse 2-loop plants |
| | * Boric acid precipitation is mitigated by starting an SI pump ~3-5 hours after the accident to supply flow to the cold legs and reactor core inlet |
| | * PBN meets the requirements in the NRC review guide on in-vessel effects |
| | - In-vessel effects have no contribution to the risk quantification 11 |
| | |
| | Risk Quantification Results |
| | * Risk quantification results for base case: |
| | - CDF on the order of 1E-08 /yr |
| | - LERF less than 1E-10 /yr |
| | * Total CDF and LERF were based on PBN PRA model of record for internal and external events |
| | - Total CDF less than 1E-04 /yr |
| | - Total LERF on the order of 1E-6 /yr |
| | * Risk increase due to strainer and reactor failures caused by LOCA-generated debris is within Region III of RG 1.174 guideline 12 |
| | |
| | Uncertainty Evaluation |
| | * Following the guidance in NUREG-1855, uncertainty evaluation addresses parametric uncertainty, model uncertainty and completeness uncertainty |
| | * Parametric uncertainty analyzed by rerunning base case model and shifting all input parameters that are not bounding to the more conservative direction |
| | - Parametric uncertainty cases showed increase in CDF but the result is well within Region III of RG 1.174 guideline |
| | * Model uncertainty quantified by replacing each non-consensus model with an alternative model |
| | - Four model uncertainty scenarios were analyzed |
| | - All model uncertainty cases showed results within RG 1.174 Region III |
| | * Completeness uncertainty qualitatively determined to be low, given over four decades of industry and NRC research and analysis in this area 13 |
| | |
| | PBN PRA Model Status |
| | * Internal events and fire PRA models developed and maintained in accordance with RG 1.200, Revision 2 |
| | * Recent NRC approved applications |
| | - TS Initiative 5.b - Surveillance Frequency Control Program |
| | - 10 CFR 50.69 |
| | - NFPA-805 |
| | * The open peer review facts and observations (F&Os) were determined to have no significant impact on the risk-informed resolution of GL 2004-02 |
| | * The relevant PRA model assumptions were reviewed and none of the assumptions are key sources of uncertainty for the risk-informed resolution of GL 2004-02 14 |
| | |
| | Submittal Content and Schedule |
| | * Submittal will address the five principles from RG 1.174 |
| | * Submittal will include the following enclosures |
| | - Enclosure 1: Request for exemption from the requirement of using deterministic methodology in 10 CFR 50.46(a)(1) |
| | - Enclosure 2: License amendment request (LAR) for implementation of risk-informed approach to address debris effects |
| | - Enclosure 3: Updated GL 2004-02 responses following the NRC content guide (revision bars will be shown for technical changes from the 2017 GL submittal) |
| | - Enclosure 4: Risk quantification and uncertainty analyses |
| | - Enclosure 5: Defense in depth measures and safety margin |
| | * NextEra is currently working on the submittal |
| | * Projected date for submittal to the NRC: Spring 2022 15 |
| | |
| | Questions?}} |
Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: ML21161A299, ML21203A314, ML21211A082, ML21214A178, ML21260A161, ML22013A339, ML22019A279, ML22061A056, ML22109A175, ML22164A861, ML22167A170, ML23188A020, ML23193A938, ML23200A183, ML23243A910, ML24067A103, ML24101A194
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MONTHYEARML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 Project stage: Meeting ML17310B2062017-11-20020 November 2017 Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 Project stage: Meeting ML18136A9052018-05-31031 May 2018 Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 Project stage: Meeting L-20-162, Supplemental Response to NRC Generic Letter 2004-022020-11-30030 November 2020 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request 0CAN122001, Final Response to NRC Generic Letter 2004-022020-12-10010 December 2020 Final Response to NRC Generic Letter 2004-02 Project stage: Request ML21062A0642021-03-0202 March 2021 NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000) Project stage: RAI NL-21-0020, Final Supplemental Response to NRC Generic Letter 2004-022021-03-23023 March 2021 Final Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request DCL-21-034, Response to Request for Additional Information on Final Supplemental Response to Generic Letter 20042021-04-15015 April 2021 Response to Request for Additional Information on Final Supplemental Response to Generic Letter 2004 Project stage: Supplement ML21118A0072021-04-28028 April 2021 Final Response and Close-out to Generic Letter 2004-02 Project stage: Request PMNS20210610, Public Meeting Regarding Path Forward for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 22021-05-17017 May 2021 Public Meeting Regarding Path Forward for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 2 Project stage: Request ML21134A0232021-05-18018 May 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC (NextEra) Project stage: Request ML21147A1462021-05-27027 May 2021 Response to Request for Additional Information Regarding Generic Letter 2004-02 Project stage: Response to RAI ML21168A2612021-06-17017 June 2021 (Vcsns), Unit 1 - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors - Final Supplemental Response Project stage: Request ML21161A2992021-06-17017 June 2021 Summary of May 18, 2021 Public Webinar with Nextera Energy Point Beach, LLC Regarding Path Forward for Generic Letter 2004-02 Closure Project stage: Other ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 Project stage: RAI ML21203A3142021-07-29029 July 2021 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML21232A0402021-08-20020 August 2021 Notice of Teleconference with Entergy Operations, Inc. Concerning Final Response to Generic Letter 2004-02 at Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting ML21252A3212021-08-20020 August 2021, 30 August 2021, 14 September 2021 ANO Meeting Summary for September 1, 2020 Public Meeting/Teleconference Project stage: Request ML21242A2792021-08-30030 August 2021 ANO Slides Presentation for 9-1-21 Public Meeting Project stage: Meeting ML21252A2662021-09-14014 September 2021 Summary of September 1, 2021, Teleconference Meeting with Entergy Operations, Inc. Concerning the Final Response to Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting ML21211A0822021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML21260A1612021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2021-09-30030 September 2021 Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request 0CAN102101, Final Request for Additional Information Concerning Generic Letter 2004-022021-10-0404 October 2021 Final Request for Additional Information Concerning Generic Letter 2004-02 Project stage: Request ML21214A1782021-10-0808 October 2021 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other PMNS20211455, Pre-Submittal Public Meeting Regarding License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 22021-12-0303 December 2021 Pre-Submittal Public Meeting Regarding License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 2 Project stage: Meeting ML21336A7972021-12-0909 December 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC - December 9, 2021 (Slides) Project stage: Request ML22019A2792022-01-20020 January 2022 Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Project stage: Other ML22019A2652022-01-27027 January 2022 Us NRC Staff Review of Documentation Provided by Firstenergy Nuclear Operating Co. for Beaver Valley, Units 1&2 Concerning Resolution of Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design B Project stage: Approval ML22013A3722022-01-27027 January 2022, 31 January 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML22013A3392022-01-31031 January 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22053A2402022-02-22022 February 2022 Final Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request ML22061A0562022-03-29029 March 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 Project stage: RAI ML22109A1752022-04-27027 April 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 Project stage: Supplement ML22164A8612022-06-24024 June 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) Project stage: Draft RAI ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 Project stage: RAI ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI Project stage: Request ML22335A4142022-12-21021 December 2022 Request for Withholding Information from Public Disclosure for Dominion Fleet Response to Request for Additional Information Regarding NRC Generic Letter 2004-02 Project stage: RAI L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information Project stage: Response to RAI L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 Project stage: Response to RAI ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23200A1832023-08-0303 August 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML24012A0492024-01-11011 January 2024 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 Project stage: RAI ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 Project stage: Response to RAI 2021-09-24
[Table View] |
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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] Category:Slides and Viewgraphs
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 ML21253A0152021-09-16016 September 2021 Pre-Submittal Meeting: LAR to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4b 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 ML18121A3392018-05-0101 May 2018 Slides for Point Beach 2017 EOC Open House ML18108A0152018-05-0101 May 2018 NextEra Approach to Resolution of Tornado Missile Protection May 1, 2018 ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17205A0192017-07-17017 July 2017 Presentation for Point Beach 2016 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 ML15203A5072015-07-28028 July 2015 July 28, 2015, Turbine Driven Auxiliary Feedwater Cross-tie License Amendment Request ML15203A4982015-07-22022 July 2015 July 2015, Containment Dome Truss Seismic Analysis Methodology License Amendment Request 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 ML13200A3962013-07-19019 July 2013 EA-13-125, Point Beach, Conference Slides ML13162A7902013-06-11011 June 2013 Meeting Slides ML1114603332011-05-25025 May 2011 EOC Licensee Presentation Slides ML1115400612011-05-25025 May 2011 Licensee Slides from 5/25/11 Public Meeting ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1107703492011-03-22022 March 2011 3/22/11 PRE-Application Meeting Slides Regarding NFPA 805 License Amendment Request ML1013802102010-05-18018 May 2010 5/18/2010 Point Beach Public Meeting Slides ML1011304452010-04-22022 April 2010 FPL Energy Point Beach Handout from End-Of-Cycle Public Meeting ML1011304972010-04-22022 April 2010 NRC Slides for Point Beach End-of-Cycle Public Meeting ML0921107842009-07-29029 July 2009 Meeting Slides, Public Meeting with NRC Region III on Point Beach ML0912007342009-04-29029 April 2009 NRC Slides for Point Beach 2008 End-of-Cycle Public Meeting ML0912007042009-04-29029 April 2009 Presentation at 2008 End-of-Cycle Public Meeting ML0912007212009-04-29029 April 2009 NRC Presentation Handouts for Point Beach 2008 End-of-Cycle Public Meeting ML0828905272008-10-14014 October 2008 Meeting with NRC on AST 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 ML0709403182007-03-28028 March 2007 EOC Summary Meeting Slides - 2007, Reactor Oversight Program - Cy 2006 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 ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0609307552006-04-0303 April 2006 Public Meeting Summary - Point Beach Safety Culture Meeting (Includes NMC Slides) ML0524903212005-08-25025 August 2005 Slides for Point Beach CAL Public Meeting Summary - August 25, 2005 ML0508304892005-03-14014 March 2005 Confirmatory Action Letter Public Meeting Slides ML0509200092005-03-0303 March 2005 3/3/05 - Preliminary Results of Environmental Review Point Beach Nuclear Plant, Units 1 and 2, Nuclear Regulatory Commission, March 3, 2005 ML0434900602004-11-30030 November 2004 NMC Slides for 11/30/04 Public Meeting ML0425404652004-08-18018 August 2004 Nuclear Management Co Confirmatory Action Letter Public Meeting Presentation Regarding Point Beach Nuclear Plant ML0508303502004-05-11011 May 2004 E-Mail B. Kemp, NMC, to H. 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Point Beach GL 2004-02 Resolution Update NextEra Energy Point Beach, LLC (NextEra)
December 9, 2021
Meeting Agenda
- Overview of Plant Layout and Strainer Configuration
- Overview of Risk-Informed Resolution Approach
- Risk and Uncertainty Quantification
- Current Status and Submittal Schedule Meeting Objectives
- Communicate current status of PBN response to GL 2004-02
- Obtain staff feedback on the overall risk-informed resolution path 2
PBN Plant Layout
- Westinghouse 2-loop pressurized water reactor (PWR) with large dry containment
- Each train has a high-head safety injection (SI) pump, residual heat removal (RHR) pump, and CS pump
- During recirculation, the CS and SI pumps take suction from the RHR pump discharge 3
Sump Strainer Arrangement Unit 1 Unit 2
- Vertical disk modules around a core tube
- Surface area of 1904.6 ft2 per train 4
Background
- Previous GL Response submitted to the NRC in 2017 (ML17363A253)
- NRC performed an audit of the submittal in January 2019 and issued an audit report in December 2019 with several questions
- PBN was able to address all questions from the audit report except for Mineral Wool cassettes having a lower destruction pressure than assumed
- NextEra conducted an alternative analysis for PBN to determine the best path for closeout of GL 2004-02
- The selected option was the use of a risk-informed resolution approach 5
Overview of Risk-Informed Approach
- PBNs risk-informed approach is similar to Vogtle
- Overall evaluation based on models that have been used in the past and accepted by the NRC for GSl-191 resolution
- Screening of break scenarios and high likelihood equipment configurations
- Multiple breaks postulated at each Class 1 weld within first isolation valve on primary loop
- NARWHAL software evaluated each primary side break to determine if it would result in strainer failures due to effects of debris
- In-vessel downstream effects analyzed in a bounding evaluation outside of NARWHAL 6
Overview of Risk-Informed Approach
- Conditional failure probabilities (CFPs) calculated for each equipment lineup and PRA break size category
- Change in core damage frequency (CDF) calculated outside PRA model using LOCA frequencies and equipment failure probabilities
- Risk contribution of secondary side breaks evaluated conservatively assuming all breaks fail the strainers due to effects of debris
- The total CDF and LERF values are obtained from the PBN PRA model
- Risk quantification results compared with RG 1.174 acceptance guidelines 7
PBN Risk-Informed Approach 8
Revision to Debris Generation Calculations
- ZOI size for mineral wool increased to 5.4D
- Mineral wool insulation is similar to K-Wool, which is classified as unjacketed mineral wool with wire mesh reinforcement in NEI 04-07
- K-Wool went through air jet impact testing and was assigned a ZOI size of 5.4D per NEI 04-07 SE
- Tested K-Wool had wire mesh lining and fabric cover
- Mineral wool insulation at PBN is encapsulated in stainless steel cassettes
- All mineral wool within the 5.4D ZOI is assumed to be fines
- Shown to be more conservative than using 17D ZOI and LDFG size distribution
- This assumption is similar to that used by Surry and North Anna 9
Acceptance Criteria for Risk Quantification
- NARWHAL software used to evaluate strainer performance
- Strainer head loss vs. pump NPSH margin and strainer structural margin NPSHr adjusted for degasification using RG 1.82 methodology
- Gas voids from degasification or flashing compared with acceptance limits
- Debris loads of a break compared with debris limits
- Head loss compared with acceptance criterion for partially submerged strainer
- Bounding analyses were performed for the following acceptance criteria
- Upstream blockage does not prevent water from reaching sump
- Pump performance not affected by air intrusion from vortexing
- Penetrated debris within ex-vessel wear and blockage limits
- In-vessel fiber load within WCAP-17788 limit for Westinghouse two-loop plant 10
Evaluation of In-Vessel Downstream Effects
- In-vessel downstream effects was analyzed outside of NARWHAL following latest NRC review guidance
- Determined total in-vessel fiber load for the bounding hot leg break using WCAP-17788 methodology
- Maximum total in-vessel fiber load is ~85 g/FA, which is less than the limit in WCAP-17788 for Westinghouse 2-loop plants
- Boric acid precipitation is mitigated by starting an SI pump ~3-5 hours after the accident to supply flow to the cold legs and reactor core inlet
- PBN meets the requirements in the NRC review guide on in-vessel effects
- In-vessel effects have no contribution to the risk quantification 11
Risk Quantification Results
- Risk quantification results for base case:
- CDF on the order of 1E-08 /yr
- LERF less than 1E-10 /yr
- Total CDF and LERF were based on PBN PRA model of record for internal and external events
- Total CDF less than 1E-04 /yr
- Total LERF on the order of 1E-6 /yr
- Risk increase due to strainer and reactor failures caused by LOCA-generated debris is within Region III of RG 1.174 guideline 12
Uncertainty Evaluation
- Following the guidance in NUREG-1855, uncertainty evaluation addresses parametric uncertainty, model uncertainty and completeness uncertainty
- Parametric uncertainty analyzed by rerunning base case model and shifting all input parameters that are not bounding to the more conservative direction
- Parametric uncertainty cases showed increase in CDF but the result is well within Region III of RG 1.174 guideline
- Model uncertainty quantified by replacing each non-consensus model with an alternative model
- Four model uncertainty scenarios were analyzed
- All model uncertainty cases showed results within RG 1.174 Region III
- Completeness uncertainty qualitatively determined to be low, given over four decades of industry and NRC research and analysis in this area 13
PBN PRA Model Status
- Internal events and fire PRA models developed and maintained in accordance with RG 1.200, Revision 2
- Recent NRC approved applications
- TS Initiative 5.b - Surveillance Frequency Control Program
- 10 CFR 50.69
- NFPA-805
- The open peer review facts and observations (F&Os) were determined to have no significant impact on the risk-informed resolution of GL 2004-02
- The relevant PRA model assumptions were reviewed and none of the assumptions are key sources of uncertainty for the risk-informed resolution of GL 2004-02 14
Submittal Content and Schedule
- Submittal will address the five principles from RG 1.174
- Submittal will include the following enclosures
- Enclosure 1: Request for exemption from the requirement of using deterministic methodology in 10 CFR 50.46(a)(1)
- Enclosure 2: License amendment request (LAR) for implementation of risk-informed approach to address debris effects
- Enclosure 3: Updated GL 2004-02 responses following the NRC content guide (revision bars will be shown for technical changes from the 2017 GL submittal)
- Enclosure 4: Risk quantification and uncertainty analyses
- Enclosure 5: Defense in depth measures and safety margin
- NextEra is currently working on the submittal
- Projected date for submittal to the NRC: Spring 2022 15
Questions?