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MONTHYEARML21022A2292021-01-22022 January 2021 Pre-Submittal Teleconference with Duke Energy Progress, LLC Regarding Brunswick Steam Electric Plant, Units 1 and 2 - Proposed Standby Liquid Control System License Amendment Request Project stage: Meeting ML21033A7022021-02-0303 February 2021 Pre-submitting for Planned LAR for Standby Liquid Control Tank Volume Increase Project stage: Approval ML21036A3112021-03-0303 March 2021 Summary of February 3, 2021, Public Meeting with Duke Energy Progress, LLC, to Discuss a Proposed LAR to Change the Standby Liquid Control System Technical Specifications for Brunswick Steam Electric Plant, Units 1 and 2 Project stage: Meeting 2021-02-03
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Category:Slides and Viewgraphs
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22109A2122022-04-20020 April 2022 Duke Energy Pre-Submittal Public April 20, 2022, Meeting Presentation ML22091A1332022-04-0101 April 2022 Bru Har Combined 2021 Assessment Meeting Slides ML21322A3262021-11-29029 November 2021 Duke Energy November 29, 2021 Pre-Submittal Public Meeting Slides for EOF Relocation Licensing Amendment Request ML21090A1162021-03-31031 March 2021 Combined 2020 Aam Presentation ML21041A4532021-02-17017 February 2021 Brunswick/Nrc Pre-submittal Meeting: LAR to Adopt TSTF-505, Rev. 2 (Risk-Informed Completion Times) Presentation ML21033A7022021-02-0303 February 2021 Pre-submitting for Planned LAR for Standby Liquid Control Tank Volume Increase ML21011A0822021-01-12012 January 2021 Pre-Submittal Meeting January 12, 2021, Revision to VRR-01, Full Stroke Testing of Safety/Relief Valves - Presentation Material ML20100G6342020-04-0909 April 2020 Revised- Bru 2019 Annual Assessment Meeting Slides ML20099C9992020-04-0808 April 2020 Har 2019 Mtg Slides ML20099D1282020-04-0808 April 2020 Bru 2019 Mtg Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML19123A3532019-05-0202 May 2019 Public Meeting Summary - Brunswick Steam Electric Plant, Docket Nos. 05000325 and 05000324 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17297B7892017-10-26026 October 2017 Meeting Slide for Partially Closed Pre-submittal Public Meeting with Duke Energy for License Amendment Request to Adopt Areva'S XM-11 Fuel Methodology for Brunswick Steam Electric Plant ML17229B2942017-08-22022 August 2017 Meeting Slide Regarding Partially Closed Pre-submittal Public Meeting with Duke Energy for a License Amendment Request for Brunswick Steam Electric Plant ML16231A1322016-08-18018 August 2016 Materials for 8/18/16 Pre-Application Meeting Brunswick Mellla+ LAR ML16210A5152016-07-28028 July 2016 Bnp Commercial Grade Dedication Issue (Printable) ML16134A1742016-05-12012 May 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Brunswick, Units 1 and 2 ML14140A1882014-05-19019 May 2014 Summary of Public Meeting - 2013 Annual Assessment Regrading Brunswick Steam Electric Plant ML14135A5092014-04-17017 April 2014 Enclosure 1 to BSEP 14-0048, Duke Energy Presentation - Brunswick Mellla+ Methods Applicability, Pre-Application Meeting ML14135A5112014-04-17017 April 2014 Enclosure 4 to BSEP 14-0048 - Areva Mellla+ Methods Applicability Presentation (Non-Proprietary Version) ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13277A0382013-09-24024 September 2013 GEH Presentation on Methods Applicability to Areva Atrium 10XM Fuel ML13277A0372013-08-20020 August 2013 Duke Energy Presentation - Brunswick Mellla+ Methods Applicability, Pre-Application Meeting, August 20, 2013 ML13130A2552013-05-10010 May 2013 4/24/2013 - Meeting Summary - Category 3 Public Meeting - Annual Assessment of Brunswick Steam Electric Plant ML12181A0362012-06-29029 June 2012 Meeting Summary - Category 1 Public Meeting - Annual Assessment of Brunswick Steam Electric Plant, Docket Nos. 50-325, 50-324 ML12158A3442012-06-0606 June 2012 Meeting Slides for Pre-Application Meeting with Carolina Power and Light Company Regarding Emergency Diesel Generator Completion Time Extension for Brunswick Steam Electric Plant, Units 1 and 2 ML11102A0052011-04-12012 April 2011 Progress Energy - Slides for NFPA 805 Pre-LAR Application Meeting April 12, 2011 ML1020304622010-07-20020 July 2010 Groundwater Protection Status ML1016705232010-06-0808 June 2010 NRC Fire Protection Screening Criteria, Brunswick Nuclear Plant ML1015404182010-05-27027 May 2010 Meeting Summary - Public Meeting - Brunswick Steam Electric Plant Annual Assessment - Reactor Oversight Program 2009 Presentation Slides ML1001507632010-01-15015 January 2010 Meeting Presentation Brunswick Nuclear Plant Human Performance ML1001507042010-01-14014 January 2010 Human Performance Slides ML0930206712009-10-22022 October 2009 Emergency Diesel Generators - Progress Energy ML1019400952009-10-0808 October 2009 Marsh, River, and Creek Tritium Results Updated 10/08/09 ML1019400932009-10-0808 October 2009 Groundwater Well Samples Results, Updated 10/08/09 ML0923210802009-08-20020 August 2009 MELLLA Plus Implementation ML0921609632009-08-0404 August 2009 Meeting Summary - Public Meeting Category 1 - Preliminary White Finding - Brunswick Steam Electric Plant ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML1019404532008-05-21021 May 2008 Email from Grzeck, Lee to Heather Gepford, Austin, Joe, George Kuzo, England, Louise, Kemp, Daniel and Dale.Dusenbury@Ncmail.Net; Subject: Storm Drain Collection Basin and Storm Drain Stabilization.Pdf; Sampling Locations Data Updated 5-19- ML0813006662008-05-0101 May 2008 EOC 2007 Progress Energy Slides ML0813006582008-05-0101 May 2008 EOC 2007 NRC Slides ML1019405012008-04-0101 April 2008 Annual Report Slides BSEP 07-0108, Areva Presentation Slides for Brunswick Fuel Transition License Amendment Request2007-07-31031 July 2007 Areva Presentation Slides for Brunswick Fuel Transition License Amendment Request ML0711503272007-04-23023 April 2007 Brunswick, EOC Slides, Cy 2006 2024-04-09
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Pre-Submittal Meeting - February 3, 2021 Standby Liquid Control Tank Volume Increase
SLC Tank Volume Increase Duke Attendees Steve Evans - Brunswick Nuclear Design Brad Lambert - Manager - Brunswick/Oconee Nuclear Design Mike Blom - Director - Fuel Management and Design Mark Turkal - Licensing Engineer Art Zaremba - Director - Nuclear Fleet Licensing Purpose Brief the NRC on scope and purpose of change Obtain NRC feedback prior to formal submittal 2
SLC Tank Volume Increase
Background
To comply with 10 CFR 50.62, BSEP uses a sodium pentaborate (SPB) solution with boron enriched to 92 atom-percent with boron-10 (B-10) isotope.
The current volume versus concentration limits in Figure 3.1.7 1 are established to ensure that the SLC system injects a quantity of boron which produces a concentration of 720 ppm equivalent of natural boron in the reactor coolant at 70°F with normal reactor vessel water level.
Purpose of LAR To accommodate core reload flexibility, the assumed 720 ppm equivalent of natural boron is being increased to 925 ppm.
Lower gadolinia loading The proposed change increases the minimum boron solution storage tank volume requirements of Figure 3.1.7-1.
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SLC Tank Volume Increase 4
SLC Tank Volume Increase The minimum allowable SPB volume from Figure 3.1.7-1 defines the equivalent concentration of natural boron used in reload SLC shutdown margin analysis.
Reactor coolant inventory at 70 deg F and normal vessel level SPB volume increased by 25% to allow for imperfect mixing, leakage and additional water volume found in small piping connected to reactor vessel No changes to B-10 enrichment, SPB concentration range OR reactor coolant inventory Increase in SPB volume is directly proportional to the increase in the natural boron concentration Proposed change is more restrictive than current Acceptable region in Figure 3.1.7-1 No plant changes are required based on recent SLC tank volume surveillances (SR 3.1.7.1) 5
SLC Tank Volume Increase The SLC System satisfies 10 CFR 50.62 (ATWS) requirements Compliance based on equivalency equation in Section 9.3.4.6 of BSEP UFSAR Proposed change does not effect equation variables 10 CFR 50.62 satisfied with same margin established with approval of MELLLA+ LAR The SLC System is also credited in the LOCA dose analysis to maintain suppression pool pH level above 7 Ensures iodine will be retained in the suppression pool water Additional SPB volume will increase suppression pool pH providing additional margin 6
SLC Tank Volume Increase Summary Increases core design flexibility and provides additional shutdown margin Does not increase range of previously approved concentration and volume combinations No impact on 10 CFR 50.62 compliance No adverse impact on ability to maintain suppression pool pH at or above 7.0 7
SLC Tank Volume Increase LAR Content BSEP 1 and 2 Tech Spec Markups (Figure 3.1.7-1)
BSEP 1 and 2 Revised Tech Spec Pages BSEP 1 Tech Spec Bases Markup For information only Schedule Planned submittal February 2021 Request approval March 2022 Required to support Unit 1 fuel cycle following spring refuel outage 8
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