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Initiation
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Results
Other: ML21161A299, ML21203A314, ML21211A082, ML21214A178, ML21260A161, ML22013A339, ML22019A279, ML22061A056, ML22109A175, ML22164A861, ML22167A170, ML23188A020, ML23193A938, ML23200A183, ML23243A910
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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 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 2021-09-14
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Category:Meeting Agenda
MONTHYEARPMNS20220468, Notice of Meeting with NextEra Energy Llc/Florida Power & Light Company2022-05-0404 May 2022 Notice of Meeting with NextEra Energy Llc/Florida Power & Light Company PMNS20220063, Notice of Meeting with NextEra Energy Llc/Florida Power & Light Company2022-02-0101 February 2022 Notice of Meeting with NextEra Energy Llc/Florida Power & Light Company 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 ML21319A2842021-11-15015 November 2021 Draft Supplemental Environmental Impact Statement Meeting Related to the Point Beach Nuclear Plant, Unit Nos. 1 and 2 (Point Beach), Subsequent License Renewal Application PMNS20211108, Public Pre-application Meeting for Proposed License Amendment Request Regarding Technical Specification Task Force (TSTF)- 505, for Point Beach Nuclear Plant Units 1 and 22021-09-13013 September 2021 Public Pre-application Meeting for Proposed License Amendment Request Regarding Technical Specification Task Force (TSTF)- 505, for Point Beach Nuclear Plant Units 1 and 2 ML21141A2322021-05-21021 May 2021 Public Meeting 6/3/21 Point Beach SLRA Fluence Concrete Steel Notice Information ML21134A0232021-05-18018 May 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC (NextEra) 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 PMNS20210090, Environmental Scoping Meeting Related to the Point Beach Nuclear Plant, Unit Nos. 1 and 2 (Point Beach), Subsequent License Renewal Application2021-02-0303 February 2021 Environmental Scoping Meeting Related to the Point Beach Nuclear Plant, Unit Nos. 1 and 2 (Point Beach), Subsequent License Renewal Application PMNS20201308, Meeting with NextEra Energy/Florida Power & Light Company to Discuss Generic Safety Issue-191/Generic Letter 2004-02 Closeout Letters2020-11-0505 November 2020 Meeting with NextEra Energy/Florida Power & Light Company to Discuss Generic Safety Issue-191/Generic Letter 2004-02 Closeout Letters ML15302A1702015-11-0202 November 2015 Forthcoming Closed Pre-Application Teleconference with NextEra Energy Point Beach, LLC (Nextera), Regarding Steam Generators H* License Amendment Request ML15183A4842015-07-0101 July 2015 Ltr. 07/01/15 Davis-Besse U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4792015-07-0101 July 2015 Ltr. 07/01/15 D.C. Cook U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting)(Drm) ML15183A4782015-07-0101 July 2015 Ltr. 07/01/15 Duane Arnold U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4722015-07-0101 July 2015 Ltr. 07/01/2015 Fermi U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4632015-07-0101 July 2015 Ltr. 07/01/15 Monticello U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4452015-07-0101 July 2015 Ltr. 07/01/15 Perry U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A3992015-07-0101 July 2015 Ltr. 07/01/15 Point Beach U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A3862015-07-0101 July 2015 Ltr. 07/01/15 Prairie Island U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15182A4412015-07-0101 July 2015 Notice and Agenda - 2015 Operator Licensing Workshop ML14169A5782014-06-13013 June 2014 Operator License Workshop Invitation ML12222A0392012-08-0909 August 2012 8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto ML12213A0612012-08-0101 August 2012 8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol ML12138A3312012-05-17017 May 2012 05/31/2012, Notice of Significant Licensee Meeting (non-public) Regarding Operator Licensing Workshop and Meeting 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 ML1106104272011-03-0707 March 2011 Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold ML1012502352010-05-0505 May 2010 Summary of the April 22, 2010, Public Meeting to Discuss the 2009 Point Beach End-of-Cycle Performance Assessment ML1011304452010-04-22022 April 2010 FPL Energy Point Beach Handout from End-Of-Cycle Public Meeting ML0921805182009-08-0606 August 2009 Notice of Public Meeting with Florida Power & Light Energy 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 ML0912007342009-04-29029 April 2009 NRC Slides for Point Beach 2008 End-of-Cycle Public Meeting ML0822503302008-10-0606 October 2008 Teleconference Summary Regarding Point Beach Nuclear Plant Supplement to the Auxiliary Feedeater Amendment ML0827307072008-09-29029 September 2008 Pre-application Meeting with FPL Energy Point Beach, LLC to Discuss Their Proposed Alternate Source Term Amendment ML0825401402008-09-16016 September 2008 Meeting Slides Point Beach Nuclear Plant Meeting with NRC on Epu. ML0821707042008-08-0606 August 2008 Notice of Meeting with FPL Energy Point Beach, LLC to Discuss the Auxiliary Feedwater License Amendment ML0634003252006-12-0707 December 2006 Notice of Presubmittal Conference for Proposed Emergency Plan Changes ML0604406422006-02-10010 February 2006 Summary of Public Meeting to Discuss Point Beach Self-Assessments, Summary Letter & Licensee Slides ML0602502942006-01-25025 January 2006 Canceled Notice of Meeting with Nuclear Management Company Regarding Fleet Transition to NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML0518203592005-07-0808 July 2005 Notice of Meeting with Nuclear Management Company Regarding the Planned Amendment to the Point Beach Nuclear Plant, Unit 1, Updated Safety Analysis Report Relating to Movement of the Reactor Vessel Head ML0520305052005-06-0303 June 2005 U1R28 OCC Interactive Turnover Meeting Agenda ML0508400622005-03-21021 March 2005 S/G Nozzle Dam Removal Pre-Job Brief Agenda ML0423600372004-08-26026 August 2004 Notice of Meeting with Industry on Risk Management Technical Specifications ML0520305002004-06-0909 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0508701682004-06-0505 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0508701652004-06-0505 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0508701612004-06-0404 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0508701632004-06-0404 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda ML0520305082004-06-0303 June 2004 U1R28 OCC Interactive Turnover Meeting Agenda 2022-05-04
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML22181B0842022-06-30030 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 ML0306407162003-02-0606 February 2003 Meeting Slides Regarding Selective Implementation of the AST for the Point Beach Fuel Handling Accident ML0226102762002-09-17017 September 2002 Meeting Handout Materials for Meeting Re Reactor Vessel Evaluation Methodologies for Point Beach, Units 1 & 2 ML0308706512002-04-29029 April 2002 NMC Viewgraphs - Point Beach Nuclear Plant Potential Common Mode Failure Auxiliary Feedwater 2022-06-30
[Table view] Category:Slides and Viewgraphs
MONTHYEARML22181B0842022-06-30030 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 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 ML1013802102010-05-18018 May 2010 5/18/2010 Point Beach Public Meeting Slides ML1011304972010-04-22022 April 2010 NRC Slides for Point Beach End-of-Cycle Public Meeting 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 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. Chernoff, NRR, May 11 Rev 2. Ppt W/Att Slides Conference Call, May 11, 2004 ML0508303302004-05-11011 May 2004 Slides: Point Beach Unit 1, Spring 2004 RPV Head Inspection Results Conference Call Tuesday, May 11, 2004 W/Handwritten Notes ML0412602942004-04-21021 April 2004 Public Meeting Slides, Point Beach 2003 End-of-Cycle Assessment ML0412602192004-04-21021 April 2004 Public Meeting Licensee Slides, Point Beach 2003 End - of - Cycle Assessment 2022-06-30
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Point Beach GL 2004-02 Resolution Update NextEra Energy Point Beach, LLC (NextEra)
May 18, 2021
Meeting Agenda
- Overview of plant layout and strainer configuration
- Resolution options evaluation
- Overview of risk-informed resolution approach
Meeting Objectives
- Communicate current Point Beach plan for GL 2004-02 response
- Obtain staff feedback on the overall risk-informed resolution path for Point Beach
- Identify areas of concern from the NRC on the approach 3
Point Beach 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 4
Sump Strainer Arrangement Unit 1 Unit 2
- Vertical disk modules around a core tube
- Surface area of 1904.6 ft2 per train 5
Background
- Previous GL Response submitted to the NRC in 2017 (ML17363A253)
- Used NEI 04-07 Section 6 alternate break methodology
- Required exemption from single failure requirement for Region II breaks
- NRC performed an audit of the submittal in January 2019
- NRC issued an audit report on December 2, 2019 with several questions
- Point Beach was able to address all technical questions from the audit report except for Mineral Wool cassettes having a lower destruction pressure than assumed 6
Resolution Options Evaluation for GL 2004-02 Closeout
- NextEra conducted an alternative analysis for Point Beach to determine the best path for closeout of GL 2004-02
- Nine options were evaluated, including different levels of modification to the resistance temperature detector (RTD) bypass line piping and/or insulation (e.g., mineral wool and Cal-Sil), use of a different resolution method, and upgrades to sump strainers
- The selected option was the use of a risk-informed resolution approach
- Accepted resolution methodology with precedence by South Texas Project (STP) and Vogtle
- The risk-informed approach addresses the NRC concerns in the audit report
- Overall risk increase due to debris effects is expected to be in Region III of Regulatory Guide (RG) 1.174
- Minimizes radiation dose associated with physical changes
- Minimizes outage impacts 7
Highlights of Changes to Overall Approach
- NextEra plans to use a risk-informed approach for Point Beach based on conditional failure probability (CFP) similar to Vogtle
- Debris generation analysis will be revised to evaluate Mineral Wool debris using a ZOI size of 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
- Mineral Wool insulation at Point Beach has a more robust casing than K-Wool Tested K-Wool had wire mesh lining and fabric cover Mineral Wool insulation at Point Beach is encapsulated in stainless steel cassettes
- BADGER models will be rerun to update debris loads for both units
- No significant updates to other deterministic analyses (e.g., debris transport, water level, etc.) or testing are anticipated 8
Event Selection for Risk Quantification
- Risk quantification will consider the following events
- Small, medium, and large LOCAs due to:
Pipe breaks Failure of non-piping components Water hammer
- Secondary side breaks inside containment that result in a consequential LOCA that requires sump recirculation
- Fire-induced RCP seal LOCAs
- Seismically-induced LOCAs
- Based on preliminary evaluations of these initiating events, it is expected that only large LOCAs and secondary side breaks will contribute to the risk associated with LOCA-generated debris 9
Secondary Side Breaks
- Secondary side breaks will be addressed using a bounding approach
- Secondary side breaks inside containment can generate a significant quantity of debris (although the ZOI would be smaller than an equivalent primary side break)
- ECCS recirculation may be necessary for secondary side breaks due to a stuck open power operated relief valve (PORV) or a scenario that requires feed and bleed
- Strainer flow rate limited by capacity of PORVs
- Internal events PRA model will be used to quantify the change in core damage frequency (CDF) and change in large early release frequency (LERF) by taking the differences in CDF and LERF between the following two scenarios:
The strainers always fail when required for secondary side breaks The strainers never fail when required for secondary side breaks
- Preliminary results indicate that the risk is within RG 1.174 Region III 10
Seismically-Induced LOCAs
- Seismically-induced LOCAs will be addressed using the Point Beach individual plant examination of external events (IPEEE)
- Large LOCAs were screened out in the IPEEE at a HCLPF (high confidence of low probability of failure) of 0.3g
- Small LOCAs were evaluated in the IPEEE and demonstrated not to be a significant risk contributor
- Because large LOCAs have a lower conditional probability of occurrence, they would also be an insignificant contributor to risk
- This conclusion is supported for the GSI-191 application because many large LOCAs would not generate enough debris to cause strainer failure Only a fraction of seismically-induced large LOCAs would contribute to strainer performance risk
- Based on this assessment, the risk contribution of seismically-induced LOCAs on strainer performance is judged to be negligible for Point Beach and screened from more detailed evaluation 11
Overview of Point Beach Risk-Informed Approach Post Accident Fiber Penetration Sump Volume Testing Debris Transport Analysis NARWHAL A break passes all failure criteria Chemical Effects Debris Analysis Generation Strainer Head Loss Analysis Testing No Yes Break fails Break passes CAD model of Various Bounding Analyses PBN Upstream effects Containment Ex-vessel wear and blockage Vortexing for bounding conditions Risk Quantification Technical and Calculate delta core License Amendment damage frequency and Request Submittals delta large early release frequency 12
Failure Criteria
- NARWHAL software will be used to evaluate each of the postulated breaks against the following failure criteria
- Strainer head loss exceeds pump NPSH margin or strainer structural margin Breaks that generate and transport more debris of any one type than tested are assumed to fail
- Gas voids from degasification or flashing exceed pump limits
- Penetrated debris exceeds in-vessel fuel blockage and boron precipitation limits In-vessel evaluation and acceptance criteria will follow latest NRC review guidance
- Bounding analysis for the following failure criteria have been performed outside of NARWHAL
- Upstream blockage prevents water from reaching sump
- Pumps fail due to air intrusion from vortexing
- Penetrated debris exceeds ex-vessel wear and blockage limits 13
Risk Quantification
- NARWHAL will be used to calculate CFPs based on:
- The definition of small (<2), medium (2-6), and large (>6) LOCAs
- The fraction of breaks that pass and fail within each size category for various pump configurations
- The LOCA frequency allocated across welds using the top-down approach
- PRA model will be used to determine the functional failure probability (FFP) for relevant equipment lineups
- All pumps available, single RHR/CS train failure, single RHR train failure, etc.
- CDF will be calculated outside the PRA model using the initiating event (LOCA) frequency, CFP, and FFP:
=
=
=0
- LERF will be calculated outside the PRA model based on:
- CDF
- Conditional large early release probability (CLERP) calculated using relevant LERF sequences from the PRA model 14
Uncertainty Evaluation
- Following the guidance in NUREG-1855, uncertainty evaluation will address:
- Parametric uncertainty
- Model uncertainty
- Completeness uncertainty
- Parametric uncertainty will quantify uncertainty associated with input parameters that are not conservative or bounding (e.g., mean LOCA frequency values)
- Model uncertainty will quantify uncertainty associated with models that are not consensus models (e.g., continuum break model) by running a sensitivity case with an alternative model (e.g., DEGB only model)
- Completeness uncertainty will be qualitatively evaluated 15
Sensitivity Analysis
- Sensitivity analysis will be performed for input parameters by varying one parameter at a time to determine its impact on the overall results
- Parameters will be varied through a range of values selected based on the value used in base case NARWHAL model
- If base case value already skewed in conservative direction, min [max] value will be assumed to be 10% lower [higher]
- If available, design limits of an input parameter will be used
- Otherwise, the min [max] value will be assumed to be 25% lower [higher] than the base case value
- Sensitivity analysis will be used to gain insights on which parameters have the most significant effect on the model 16
Submittal Content and Schedule
- Submittal will address the five principles from RG 1.174
- Submittal will include the following enclosures
- Enclosure 1: License amendment request (LAR) for implementation of risk-informed approach to address debris effects
- Enclosure 2: Request for exemption from 10 CFR 50.46(a)(1) for the use 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 sensitivity and uncertainty analyses
- Enclosure 5: Defense-in-depth measures and safety margin
- Complete analyses: October 2021
- Submittal updates: December 2021
- Submittal to the NRC: Spring 2022 17
Point Beach PRA Model Status
- Internal events PRA model developed and maintained in accordance with ASME/ANS PRA standard and RG 1.200, Revision 2
- TS Initiative 5.b - SFCP
- 10 CFR 50.69
- NFPA-805
- A preliminary assessment of the open peer review facts and observations (F&Os) indicates they will have no significant impact on the risk-informed resolution of GL 2004-02
- A preliminary review of relevant PRA model assumptions indicate that none of the assumptions are key sources of uncertainty with respect to the risk-informed resolution of GL 2004-02 18
Questions?