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Category:Meeting Agenda
MONTHYEARPMNS20240480, Notice of Meeting with Entergy Operations Inc2024-04-15015 April 2024 Notice of Meeting with Entergy Operations Inc PMNS20231406, Presubmittal Meeting with Entergy Operations, Inc. for a Proposed Online Monitoring License Amendment Request2024-01-11011 January 2024 Presubmittal Meeting with Entergy Operations, Inc. for a Proposed Online Monitoring License Amendment Request PMNS20231101, Meeting Notice with Entergy Operations, Inc. Regarding a Presubmittal License Amendment Request for Arkansas Nuclear One, Unit 2 and Waterford Steam Electric Station, Unit 32023-10-0202 October 2023 Meeting Notice with Entergy Operations, Inc. Regarding a Presubmittal License Amendment Request for Arkansas Nuclear One, Unit 2 and Waterford Steam Electric Station, Unit 3 PMNS20230582, Presentation to the St. Charles Parish Council of the Nuclear Regulatory Commission'S 2022 Annual Assessment of Safety Performance at Waterford Unit 3 Steam Electric Station2023-05-0202 May 2023 Presentation to the St. Charles Parish Council of the Nuclear Regulatory Commission'S 2022 Annual Assessment of Safety Performance at Waterford Unit 3 Steam Electric Station PMNS20221160, Notice of Closed Meeting with Entergy Operations Inc. to Discuss Security Program Strategy Changes Applicable to the Entergy Fleet2022-11-0404 November 2022 Notice of Closed Meeting with Entergy Operations Inc. to Discuss Security Program Strategy Changes Applicable to the Entergy Fleet PMNS20220993, Notice of Meeting with Entergy Operations, Inc. Regarding Waterford Steam Electric Station, Unit 32022-09-29029 September 2022 Notice of Meeting with Entergy Operations, Inc. Regarding Waterford Steam Electric Station, Unit 3 ML22224A2462022-08-19019 August 2022 Entergy Slides for Regulatory Conference (Enc 3) PMNS20220738, Notice of Public Meeting, Licensee: Entergy Operations, Inc., Facility: Waterford Steam Electric Station, Unit 32022-07-18018 July 2022 Notice of Public Meeting, Licensee: Entergy Operations, Inc., Facility: Waterford Steam Electric Station, Unit 3 PMNS20220554, Meeting Notice with Entergy Operations, Inc. Regarding a Presubmittal of a Relief Request for Grand Gulf Nuclear Station, Unit 1, River Bend Station, Unit 1, and Waterford Steam Electric Station, Unit 32022-06-0909 June 2022 Meeting Notice with Entergy Operations, Inc. Regarding a Presubmittal of a Relief Request for Grand Gulf Nuclear Station, Unit 1, River Bend Station, Unit 1, and Waterford Steam Electric Station, Unit 3 PMNS20220467, Public Webinar to Discuss the Nuclear Regulatory Commission'S 2021 Annual Assessment of Safety Performance at Region IV Plants2022-05-0303 May 2022 Public Webinar to Discuss the Nuclear Regulatory Commission'S 2021 Annual Assessment of Safety Performance at Region IV Plants PMNS20211431, Notice of Presubmittal Meeting with Entergy Operations, Inc2021-11-17017 November 2021 Notice of Presubmittal Meeting with Entergy Operations, Inc ML21134A2122021-05-21021 May 2021 Audit Meeting Agenda and Audit Questions for LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components for Nuclear Power Reactors PMNS20210563, Public Webinar to Discuss the NRCs 2020 Annual Assessment of Safety Performance at Arkansas Nuclear One, Columbia, Comanche Peak, Cooper, Diablo Canyon, Palo Verde, River Bend Station, South Texas Project, Waterford, and Wolf Creek2021-04-29029 April 2021 Public Webinar to Discuss the NRCs 2020 Annual Assessment of Safety Performance at Arkansas Nuclear One, Columbia, Comanche Peak, Cooper, Diablo Canyon, Palo Verde, River Bend Station, South Texas Project, Waterford, and Wolf Creek PMNS20201419, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32021-02-0505 February 2021 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors PMNS20201357, Meeting with Entergy Operations, Inc. to Discuss a Proposed License Amendment Request for Relocating Technical Specifications to the Technical Requirements Manual for Waterford Steam Electric Station, Unit 32020-12-0404 December 2020 Meeting with Entergy Operations, Inc. to Discuss a Proposed License Amendment Request for Relocating Technical Specifications to the Technical Requirements Manual for Waterford Steam Electric Station, Unit 3 PMNS20201358, Meeting with Entergy Operations, Inc. to Discuss a Proposed License Amendment Request for Adopting Risk-Informed Technical Specification Completion Times for Waterford Steam Electric Station, Unit 32020-12-0404 December 2020 Meeting with Entergy Operations, Inc. to Discuss a Proposed License Amendment Request for Adopting Risk-Informed Technical Specification Completion Times for Waterford Steam Electric Station, Unit 3 PMNS20201195, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 PMNS20201232, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 PMNS20201233, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 PMNS20201234, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 PMNS20201184, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-0707 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 ML20170B1872020-06-19019 June 2020 Public Webinar to Discuss the Nrc'S Assessment of Safety Performance at Region IV Plants for 2019 ML18093A4872018-04-17017 April 2018 Public Teleconference Regarding Request for Alternative to the Requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, IWA-5211, for the Waterford Steam Electric Station, Unit 3 ML15082A4442015-03-23023 March 2015 Regulatory Conference with Entergy Operations, Inc ML14024A2912014-01-24024 January 2014 Notice of Meeting with Entergy Operations, Inc., to Discuss Its National Fire Protection Association (NFPA) 805 License Amendment Request Supplement Changes for the Waterford Steam Electric Station, Unit 3 ML14023A2792014-01-23023 January 2014 Notice of Meeting with Entergy Operations, Inc., to Discuss Waterford Unit 3 License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition ML1125904152011-09-16016 September 2011 Regulatory Conference with Waterford Steam Electric Station, Unit 3, to Discuss the Significance, Cause, and Corrective Action Associated with a Preliminary Finding with Low-to-moderate Safety Significance (White) ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1030600782010-10-27027 October 2010 Corrected Notice of Meeting with Entergy Operations, Inc. to Discuss Request for Additional Information for Waterford Unit 3 License Amendment Request to Approve FSAR Change for Leak-Before-Break of the Pressurizer Surge Line ML1030101052010-10-27027 October 2010 Correction 11/10/10 Meeting Notice with Entergy Operations, Inc. to Discuss Request for Additional Information for Waterford Unit 3 License Amendment Request to Approve FSAR Change for Leak-Before-Break of the Pressurizer Surge Line ML1029904062010-10-27027 October 2010 Notice of Meeting with Entergy Operations, Inc. to Discuss Request for Additional Information for Waterford Unit 3 License Amendment Request to Approve FSAR Change for Leak-Before-Break of Pressurizer Surge Line ML1013400612010-05-18018 May 2010 Notice of Forthcoming Conference Call with Entergy Operations, Inc. to Discuss Draft Response on GL-2004-02 for Waterford Steam Electric Station, Unit 3 ML1005400832010-02-24024 February 2010 Forthcoming Conference Call with Entergy Operations, Inc. to Licensee'S Responses to NRC Generic Letter 2004-02 for Waterford Steam Electric Station, Unit 3 ML0927500102009-10-0202 October 2009 Revised Notice of Conference Call with Entergy Operations, Inc. to Discuss Waterford Steam Electric Station, Unit 3, Planned Response to Request for Additional Information on Generic Letter 2004-02 ML0927200322009-10-0101 October 2009 Notice of Forthcoming Conference Call with Entergy Operations, Inc. to Discuss Waterford Steam Electric Station, Unit 3, Planned Response to Request for Additional Information on Generic Letter 2004-02 ML0924702992009-09-0808 September 2009 Notice of Closed Meeting with OGC, OE, RGN-IV and NSIR to Discuss Entergy'S Assessment of the Waterford 3 Security Baseline Inspection and Special Inspection Conducted by the NRC ML0922302632009-08-13013 August 2009 Notice of Meeting with Entergy Operations, Inc., to Discuss Leak-Before-Break Methods for Waterford Steam Electric Station, Unit 3, Surge Line ML0923104632009-08-13013 August 2009 August 27, 2009 Notice of Cancelled Meeting with Entergy Operations, Inc., to Discuss Leak-Before-Break Methods for Waterford Steam Electric Station, Unit 3, Surge Line ML0807100082008-03-11011 March 2008 Notice of Meeting with Arizona Public Service, Entergy Operations, Inc., Exelon Generation Co., FPL Energy, Luminant Generation Co., South Carolina Electric & Gas Co., STP Electric Generating Co., & Southern Nuclear Operating Co ML0726701082007-10-10010 October 2007 9/06/2007 Waterford Steam Electric Station, Unit No. 3 - Meeting Handouts ML0722104392007-08-13013 August 2007 Notice of Forthcoming Meeting with Entergy Operations, Inc. - Outline Plans for Mid-Cycle Outage Steam Generator Batwing Issues at Waterford Steam Electric Station, Unit 3 ML0705304582007-02-26026 February 2007 Notice of Meeting with Entergy Operations, Inc. Steam Generator Batwing Design Issue - Waterford Steam Electric Station, Unit 3 ML0607600462006-03-17017 March 2006 Meeting Agenda for 04/05/2006, Forthcoming Meeting with Entergy Operations, Inc., Regarding Waterford 3 Design Issue ML0504006142005-01-26026 January 2005 Transcript of ACRS Thermal Hydraulic Phenomena Subcommittee Meeting on Waterford 3 Extended Power Uprate Project, January 26, 2005 ML0430905692004-11-0404 November 2004 Notice of Meeting with Entergy Waterford, Unit 3 - Extended Power Uprate Application ML0423904892004-08-26026 August 2004 Meeting with Entergy to Discuss Issues with Extended Power Uprate and Alternate Source Term Submittals ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback 2024-04-15
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24248A2362024-09-0404 September 2024 2023 Annual Assessment Meeting Slides ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML22271A7502022-09-29029 September 2022 Preapplication Meeting Slides: Technical Specification Change to Support Elimination of ESFAS Single Point Vulnerability ML22224A2462022-08-19019 August 2022 Entergy Slides for Regulatory Conference (Enc 3) ML22217A0082022-07-29029 July 2022 Regulatory Conference - NRC Slides (Enc 2) ML22076A1962022-03-17017 March 2022 Presentation March23, 2022 NRC Di_C Workshop ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor ML21013A3362021-01-26026 January 2021 December 17, 2020, Summary of Category 1 Public Pre-Application Meeting with Entergy Operations,Inc. Regarding Proposed LAR to Adopt Risk-Informed TS Allowed Outage Times for Waterford Steam Electric Station, Unit 3 ML21013A3372020-12-17017 December 2020 Risk-Informed Allowed Outage Time (Riaot) License Amendment Request -NRC Pre-Submittal Meeting, Licensee Slide Presentation, December 17, 2020 EPID L-2020-LRM-0110 ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20288A7292020-09-22022 September 2020 Presentation Cpc/Ceac Replacement License Amendment Request - September 22, 2020 W3F1-2020-0017, Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2020-03-12012 March 2020 Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification W3F1-2019-0082, Transmittal of Slides for Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2019-12-0505 December 2019 Transmittal of Slides for Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification W3F1-2019-0068, Transmittal of Slides for Presubmittal Public Meeting to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2019-09-12012 September 2019 Transmittal of Slides for Presubmittal Public Meeting to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18037B1102018-02-0808 February 2018 Presentation Slides for February 8 2018 Preapplication Meeting to Discuss Chapter 15 Fuel Misload ML17290A6552017-10-19019 October 2017 Public Meeting, Licensee Presentation Slides Regarding Waterford, Unit 3, Fluence Methodology ML16190A0842016-06-0808 June 2016 Public Meeting, June 8, 2016 (Pmc Comments1) ML15222A3472015-08-11011 August 2015 Presentation for 8-11-15 Public Meeting on Main Control Room Abandonment ML15196A4152015-07-15015 July 2015 Summary of Meeting with Entergy Corporation to Discuss Annual Performance Assessment ML15113A7872015-04-22022 April 2015 CEA Drop Time Technical Specification Change Request April 22, 2015 Revised Public Meeting Slides ML15110A0622015-04-22022 April 2015 CEA Drop Time T.S. Change Request April 22,2015 Public Meeting Slides ML14035A0942014-02-0404 February 2014 2/4/2014 Waterford Steam Electric Station, Unit 3 - Meeting Slides - NFPA 805 LAR Supplement ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML12261A1962012-09-16016 September 2012 Summary of Meeting with Waterford Steam Electric Station to Discuss the Performance of the Waterford Steam Electric Station, Unit 3, for the Period of July 1, 2011 Through June 30, 2012 ML1129205202011-10-19019 October 2011 Regulatory Conference Summary ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1031403752010-11-10010 November 2010 Handouts for the 11/10/10 Meeting Regarding Surge Line Leak-Before Break RCS Leakage Detection ML1014606312010-05-26026 May 2010 Summary of Public Meeting with Entergy Operations on Waterford Steam Electric Station Unit 3 2009 Performance ML1006903722010-03-0808 March 2010 Licensee Slides from 3/8/2010 Meeting Generic Letter 2004-02 Response to RAIs ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0821401432008-07-31031 July 2008 Summary of Public Meeting with Entergy on Waterford, Unit 3, 2007 Performance ML0805102512008-02-20020 February 2008 Summary of Meeting with Entergy Operations, Inc. Degraded Batwings Metal Support Structures for Tubes in Waterford 3's Steam Generators ML0729806702007-10-24024 October 2007 Meeting Presentation on GEH Chemical Effects Testing Update ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0726701082007-10-10010 October 2007 9/06/2007 Waterford Steam Electric Station, Unit No. 3 - Meeting Handouts ML0712005272007-04-30030 April 2007 Nrc/Entergy Operations, Inc. Management Meeting to Discuss the Performance of Arkansas Nuclear One, Cooper, Grand Gulf, River Bend and Waterford, Unit 3 ML0708706752007-03-22022 March 2007 Meeting Slides, Entergy Meeting with NRC, Topic: Waterford 3 Batwings ML0615000942006-05-30030 May 2006 Summary of Meeting with Entergy Operations Re Waterford Steam Electric Station, Unit 3, Annual Performance Assessment ML0610103332006-04-0505 April 2006 Slides Presented at April 6, 2006 Waterford 3 Meeting ML0427901372004-10-0404 October 2004 Meeting Summary for the September 29, 2004, Public Meeting to Discuss General Engineering Related Topics ML0323705292003-08-22022 August 2003 Summary of Nrc/Entergy Operations, Inc. Management Meeting ML0323201802003-08-14014 August 2003 8/14/03, EOI Will Discuss Its May 8, June 11, & July 1, 2003, Relaxation Requests from Nrc'S Vessel Head Inspection Order ML0310102992003-04-0101 April 2003 Enclosures to 04/01/2003 Waterford End-of-Cycle Meeting Summary. Includes Attendance List & Copy of Slides Presented 2024-09-04
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24248A2362024-09-0404 September 2024 2023 Annual Assessment Meeting Slides ML24096B4992024-04-0101 April 2024 Slides: Pre-Submittal Meeting for License Amendment Request to Modify Selected Surveillance Requirements in Support of the Surveillance Frequency Control Program ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML23122A1012023-05-0202 May 2023 Assessment Presentation 2022 ML22271A7502022-09-29029 September 2022 Preapplication Meeting Slides: Technical Specification Change to Support Elimination of ESFAS Single Point Vulnerability ML22224A2462022-08-19019 August 2022 Entergy Slides for Regulatory Conference (Enc 3) ML22217A0082022-07-29029 July 2022 Regulatory Conference - NRC Slides (Enc 2) ML22164A8012022-06-13013 June 2022 Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides ML22076A1962022-03-17017 March 2022 Presentation March23, 2022 NRC Di_C Workshop ML21319A2452021-11-15015 November 2021 Natrium Energy Island Decoupling Strategy - 11-17-2021 ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21306A3162021-11-0909 November 2021 Digital IC Presentation 11/09/2021 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor ML21013A3362021-01-26026 January 2021 December 17, 2020, Summary of Category 1 Public Pre-Application Meeting with Entergy Operations,Inc. Regarding Proposed LAR to Adopt Risk-Informed TS Allowed Outage Times for Waterford Steam Electric Station, Unit 3 ML21012A1982021-01-15015 January 2021 Relocate Toxic Gas Monitoring Technical Specifications to Technical Requirements Manual License Amendment Request - NRC Pre-submittal Meeting ML21013A3372020-12-17017 December 2020 Risk-Informed Allowed Outage Time (Riaot) License Amendment Request -NRC Pre-Submittal Meeting, Licensee Slide Presentation, December 17, 2020 EPID L-2020-LRM-0110 ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20288A7292020-09-22022 September 2020 Presentation Cpc/Ceac Replacement License Amendment Request - September 22, 2020 W3F1-2020-0017, Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2020-03-12012 March 2020 Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification W3F1-2020-0002, Transmittal of Slides for Third Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2020-01-0808 January 2020 Transmittal of Slides for Third Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification W3F1-2019-0082, Transmittal of Slides for Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2019-12-0505 December 2019 Transmittal of Slides for Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification W3F1-2019-0068, Transmittal of Slides for Presubmittal Public Meeting to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2019-09-12012 September 2019 Transmittal of Slides for Presubmittal Public Meeting to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML18037B1102018-02-0808 February 2018 Presentation Slides for February 8 2018 Preapplication Meeting to Discuss Chapter 15 Fuel Misload ML17318A1232017-11-16016 November 2017 Licensee Presentation Slides for November 16, 2017, Category 1 Public Meeting Regarding Engineered Safety Features Actuation System ML17306A1652017-11-0202 November 2017 Updated Licensee Slide Presentation for October 19, 2017 Category 1 Meeting Regarding Raptor ML17290A6552017-10-19019 October 2017 Public Meeting, Licensee Presentation Slides Regarding Waterford, Unit 3, Fluence Methodology ML17158B1502017-06-0808 June 2017 Meeting Slides for High Pressure Safety Injection Pump AB Pre-submittal Public Meeting Relief Request Per 50.55a(Z)(2)for Waterford Steam Electric Station, Unit 3 ML17151A2952017-06-0101 June 2017 6/1/2017, Meeting Slide for Pre-Submittal Meeting Regarding Ultimate Heat Sink Technical Specification Change Request for Waterford 3 ML17101A6482017-04-11011 April 2017 Public Meeting Slides ML16190A0842016-06-0808 June 2016 Public Meeting, June 8, 2016 (Pmc Comments1) ML15222A3472015-08-11011 August 2015 Presentation for 8-11-15 Public Meeting on Main Control Room Abandonment ML15196A4152015-07-15015 July 2015 Summary of Meeting with Entergy Corporation to Discuss Annual Performance Assessment ML15113A7872015-04-22022 April 2015 CEA Drop Time Technical Specification Change Request April 22, 2015 Revised Public Meeting Slides ML15110A0622015-04-22022 April 2015 CEA Drop Time T.S. Change Request April 22,2015 Public Meeting Slides ML14035A0942014-02-0404 February 2014 2/4/2014 Waterford Steam Electric Station, Unit 3 - Meeting Slides - NFPA 805 LAR Supplement ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML12261A1962012-09-16016 September 2012 Summary of Meeting with Waterford Steam Electric Station to Discuss the Performance of the Waterford Steam Electric Station, Unit 3, for the Period of July 1, 2011 Through June 30, 2012 ML11321A2912011-11-17017 November 2011 Final Significance Determination of White Finding, NRC Inspection ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1031403752010-11-10010 November 2010 Handouts for the 11/10/10 Meeting Regarding Surge Line Leak-Before Break RCS Leakage Detection ML1014606312010-05-26026 May 2010 Summary of Public Meeting with Entergy Operations on Waterford Steam Electric Station Unit 3 2009 Performance ML1006903722010-03-0808 March 2010 Licensee Slides from 3/8/2010 Meeting Generic Letter 2004-02 Response to RAIs ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0909603272009-04-0606 April 2009 Summary of Public Meeting with Entergy on Waterford Steam Electric Station Unit -3 2008 Performance 2024-09-04
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Text
Entergy - Waterford 3 Meeting with NRC on Steam Generator Batwing Issue September 6, 2007 1
Introduction
- Conservative Operational Assessment
- Defense in depth mitigation strategy
- Conservative monitoring and action limits
- Heightened awareness (ODMI)
- Conservatively performing a mid-cycle
- Inspection scope
- Expected findings
- Contingency criteria and planning 2
Agenda Discussion Topic Presenter Time Overview of Batwing Keith Nichols 5 Mitigation Strategy Steam Generator Monitoring Keith Nichols 5 Update Mid-Cycle Planned Activities Rex Putnam 30 Mid-Cycle Contingencies and Rex Putnam 40 Criteria Mid-Cycle Communication Bob Murillo 5 Plan Summary and Q&A Joe Kowalewski 10 3
Overview of Batwing Mitigation Strategy Keith Nichols 4
SG 32 - Status
- 22 broken batwings in stay cavity region
- Wrap Around Bar welds in the stay cavity region have been inspected and reinforced except BW at Column 84/85 (cold leg)
- Column 84/85 (cold leg) batwing slid into the tube bundle
- held in place by tube friction
- Adjacent tubes were plugged, sentinel plugged, or plugged and stabilized 5
Waterford ý3 Steam Generator 32 Batwing Inspection from Lower Handhole Approximate Position of Slotted Bar HL Batwing with Broken ..
Weld (Columns 1081109) Approximate Original Location of CL Batwing with Broken Weld 44 '4 ~44~'.
(Columns 84/85 Cold Leg) 44 44 44~ 44'~~4~
Batwing Tube Support "444 444444 4'
'.444 444 4 "<".44 Approximate Location Broken at Notch >i 4444 j '44444 >44 RF13 Batwing Failures 44 ~444> ~'.
(Columns 82/83/84) 4'4.4
'..444.444
.'4444.
~444 4 44 4 4444 K
Cold Leg Hot Leg
~4~44 44 '"' ' 444>4 4444 r Loose Batwing Bar 4 4 2 Batwings Broken at Weld
.. 4*
44 9'. ".9~
44~
~44 4
'44 44 4 444 44 Abrasive Wear 6 On Top Support Plate
Refuel-14 Repairs Defense-in-depth mitigation strategy
- Analysis of potential loose parts
- Analysis and validation of tube wear rates
- Analysis of forces on welds for batwing to wrap around bar
- Batwing welds to wrap around bar in SG 2 enhanced for batwings that traverse through stay cavity
- Inner row of tubes around stay cavity and loose batwing are plugged and stabilized
- Sentinel plugs added in on wrap around bar perimeter, around stay cavity and around loose batwing 7
SG - 32 TUBE REPAIR HISTORY RF 13 AND RF14 - E,,"4 Watefford RF0.1 z ,,%T, 3 -. 1C L I - --
-::-R # 7 STAY PCSIT:ON
- i3 Li 22
.22
'4l 22 i
ilH 443
'I 7-4 .~1 7-7,0
--. 7-1: -777:7. 7 7
.
'.2 A
.0. .. . .. .0. .. .0 4 4.2 2'.
- 44 22 is. 00070 704 - ~2 4.4 77. ..
1 1,:ýH 1 L.- A PA. fa IE S '.4s I; IVi l+'Q M Ile 1W. 100 ýI Sý Ai A S . -V r I Preventive Plugging also in SG#1
Steam Generator Monitoring Update Keith Nichols 9
SG Monitoring Update Summary
" Dedicated loose parts monitor installed to monitor SG
- No metallic impacts identified
" Operational Decision Making Issue for primary to secondary leak rate
- 0.5 gpd steady and consistent with previous cycle
- 2 gpd and 5 gpd triggers increased monitoring and evaluation
- 5 gpd with a rate of 7.5 gpd/hr administrative shutdown
- 15 gpd administrative shutdown
- High level of site awareness and sensitivity
- Seven tube leak simulator training sessions this year with each operating crew
- Operations, Engineering and Chemistry monitoring 10
Steam Generator Primary to Secondary Leak Rate 3.00-2.50 2.00 4 a.
1.0 0
1.00 0.00 1/1/04 7/19/04 2/4/05 8/23/05 3/11/06 9/27/06 4/15/07 11/1/07 Date 11
Mid-Cycle Planned Activities Rex Putnam 12
Mid-Cycle Inspection Purpose
" Visually inspect the secondary side of the steam generators for the purpose of:
- determining any unforeseen extent of condition
- determining any unforeseen change in the critical variables that were the basis for the repair plan and operational assessment
- Secondary inspections will confirm no unforeseen changes
- BW to Wrap Around Bar Interface [Weld, Clip, Deformation]
- Examine Stay Cavity (Bottom Up) for Visible Deformation of the Tube Bundle
- A BW segment extending beyond the Seventh Eggcrate Support
- A BW segment outside of the stay cavity region
° Conservative Operational Assessment
- RF14 Operational Assessment predicted margin for all mechanisms
- Batwing related tube wear model was validated in RF14
- Forces (and thus wear) attenuates as the batwing extends further into the tube bundle
- Open tubes would not be impacted until after the Sentinel plugged tubes
- Sentinel plugged tubes remain intact
- Active tubes are not expected to have significant wear for 16 years 13
Mid-Cycle Inspections Secondary visual exam of upper batwings
° verify no upper batwing weld/clip failures in stay cavity area
- verify no gross deformation twisting of wrap around bar Foreign object search and retrieval
- remove accessible foreign objects
° no batwing segment outside of stay cavity Secondary.visual inspection of stay cavity area
- monitor batwing degradation
- verify that batwing at column 84/85 cold leg has not dropped Secondary diagonal visual inspection of upper stay cavity area (SG2 only)
- provide additional information in support of repair options in RF15 14
Upper Batwing Visual Inspection
" Critical Variable: No additional batwings have slipped into the tube bundle and no wrap around bar deformation
" Inspection: Visual exam to verify no upper weld failures for batwings instay cavity area and no gross deformation twisting of wrap around bar
" Analysis: Wear growth rates and wear distribution.
15
FOSAR Inspection e Critical Variable: No large mass foreign objects
- Inspection: Foreign object search and retrieval and visual inspection
- Analysis: Ginna tube rupture event analysis jinvolved the repeated impacts of a large mass foreign object over several years.
16
FOSAR Inspection 9 Critical Variable: Effectiveness of stabilizer fence for containing loose segments and maximum size of loose batwing segments in stay cavity 0 Inspection: Visual exam of stay cavity region and FOSAR to verify no large batwing segments or segments outside stay cavity e Analysis: Broken batwing analyses assumed containment of BW segment in stay cavity region to evaluate acceptabilityof tube impacts and wear, including normal and accident condition 17
Visual Inspection of Stay Cavity
- Critical Va riable: No extruded batwings 0l1 nspection: Visual inspection of stay cavity area for extruded BW segments 9 Analysis: Loose parts analysis for impact and wear. Note that attenuation analysis is conservatively based on a maximum force determined by BW materialplus sail area.
18
450 Inspection
- Provide additional information for RF15 repair options
- Inspection contingencies are developed 19
Expected Batwing Condition
- Upper batwing welds should be intact.
- Stay cavity damage has not been observed, but is possible. A mitigation strategy similar to that used in SG2 was applied in SG1 in RF-14.
- Upper batwing welds/clips and wrap around bar should be intact
- Propagation of batwing damage in the stay cavity is expected
- No indications of gross tube deformation is expected
- Column 84/85 batwing may move but is not expected to damage the stabilizer fence or active tubes
- Stabilized tubes around the stay cavity may have visible through wear but tube and stabilizer are expected to remain structurally intact
- No gross tube damage is expected 20
Secondary Inspection Techniques 21
Wrap Around Bar Inspection Tooling
- Access wrap around bar from steam drum
- Guide hooks on the wrap around bar
- Video probe inserts into guide tube for inspection
Wrap Around Bar Inspection Results
'C" ~
23
Lower Batwing Visual Inspection Tooling
- Installs through secondary 4 handhole at *....., :* . . . .*.}"..*!
....,...... . * ....
tubesheet/ *:~~~~.. . ..*......*:.*
.*....._.,.
18x fixed I.....'"-
magnification K___________
24
Waterford 3 Steam Generator 32 Batwing Inspection from Lower Handhole Approximate Position of Slotted Bar HL Batwing with Broken S*
Weld (Columns 108/109) . Approximate Original
,*
- ,,*.:** ...!. . Location of CL Batwing with Broken Weld (Columns 84/85 Cold Leg)
Batwing Tube Support Approximate Location 4...
Broken at Notch 4.'
RF13 Batwing Failures (Columns 82/83/84) 44.4.4~4.~
'-A'
,.*. .*;*.*;.*j ....*
- Cold Leg Loose Batwing Bar
~ ..- 4., . 44444'4~ 44.4.
..................
44444~.444.".
~ .444~
44*
44 ~ 44.44 4 '4 2 Batwings Broken at Weld Abrasive Wear 25 N
On Top Support Plate
Area to be examined where Batwings enter tube bundle (heavy line)
Cutaway of central stay cavity 26
First of a Kind Diagonal Inspection 0-090' TYP 0.66SIR, 0.5.
.......... VETPERODI OT1 0.09(r 1yý
-.0 SI] TC UPPER TUBE BUNDLE SLUDGE LANCING (Flowstream Width = 0.48 in.)
27
Waterford Project Overview
- Diagonal Inspection Development Milestones Westinghouse Letter LTR-NFSM-07-118 "Diagonal Inspection and April 07 Mockup Requirements" Brooks Specification FS 55-05 "Diagonal Inspection Specification May 07 Requirements" Mockup and Tooling Design June 07 Mockup and Tooling Material Procurement June 07 Lower and Upper Mockup and Tooling Fabrication July 07 Video Probe and Tooling Prototype, Dry Mockup Testing August 07 Video Probe and Tooling Prototype, Wet Mockup Testing August 07 Video Probe and Tooling Final Design Development August 07 Video Probe and Tooling Final Manufacturing and Testing September 07 Video Probe and Tooling Qualification Testing September 07
- Mockup Tests were witnessed by Westinghouse and Waterford 3 personnel at Brooks 28
Mock-up of Upper Stay Cavity
- Simulates the upper7 stay cavity region ...
- Limited draw back space (21)
-- Jam Uio -
29
Mock-up of Upper Stay Cavity 450 Inspection
- This is a view of the mockup .
showing the tube to batwing interface Mockup test is underwater in dark environment .
Guide tube is .40" thick in a .48 gap Area of interest for '
diagonal inspection 30
Mock-up of Upper Stay Cavity
- Mock-up is inthe tank and includes platform to closely represent correct distance to entry point
~ 17 A
~L4
~ ~-~---
y
.....................................................................
~
I.
.,
.
31 V
Mock-up of Upper Stay Cavity 450 Inspection Mockup photo from video probe in wet and "
dark environment 450 inspection mock-up testing was successful ,K ,
- Able to see tube to batwing interface
- Able to see tube and batwing degradation
- Able to see 1-3 tubes in bundle Batwing to tube interface 32
Mid-Cycle Planned Activities Summary
- Secondary inspections (Upper, Lower and FOSAR) will verify that the critical variables used for the repair plan and operational assessment are met
- 450 inspection mock-up testing has been successful and will help establish RFI5 repair plan 33
Mid-Cycle Contingencies and Criteria Rex Putnam 34
Contingency Planning
- The potential outcomes of each secondary inspection activity were evaluated
- Appropriate contingencies planning has been taken SA .comprehensive decision flow chart has been prepared
- As found conditions will be evaluated and contingencies implemented as necessary 35
Decision Matrix Purpose
- Assures a consistent pre-thought decision for credible secondary inspection outcomes for conditions that cannot be accepted
- Reviews assure consistency with technical analyses
- Used to establish level of contingency planning and resource allocation
" Assures a thorough communication of specific decisions and criteria
" Facilitates rigorous and timely decision-making during the outage
" Labeled decision blocks and actions have written guidance explaining criteria and intended actions Color coded for previously described contingency action 36
Mid-Cycle Outage Contingencies
- Decision chart contingencies are color coded for ease of use.
- Eddy Current Test
- Install new 6" Access Port
- Batwing Weld Repair
- Batwing Stabilization 37
Wrap Around Bar Inspection Contingencies (Chart I)
Weld/clip failures in stay cavity area
- Indicated by irregular spacing and detached batwings with separation to a weld remnant on the wrap around bar and comparison with as-left video from RF14.
- If batwing has migrated into the tube bundle, contingency is to bobbin test the open tubes on both sides of the displaced batwing to locate it, then perform Plus Point testing of tubes with identified wear
- If batwing is retrievable, contingency is to re-weld the batwing to the diagonal bar using same repair plan used in RF14 38
Wrap Around Bar Inspection Contingencies (Chart I)
Gross deformation twisting of wrap around bar
- Indicated by visible twisting deformation of the wrap around bar and multiple nearby adjacent batwing cross-sections with a scuff, gouge or indentation indicating possible shroud impact. Damage would be confirmed by comparison with as-left video from RF14.
- Contingency is to bobbin test 5 open tubes per column for 5 columns on each side of the damage and Plus point identified wear. Develop and implement repair plan, such as a support attached to the wrap around bar.
39
Diagonal Tube Bundle Inspection Contingencies (Chart Ill)
Gross tube damage is identified
° Indicated by irregular tube spacing, tube dislocation, through-wall wear greater than one-third of the tube.
- Contingency is to bobbin test 5 open tubes per column closest to the damage and plus point identified wear. If stabilized tube, evaluate and determine whether needed to deplug and stabilize next tube in column to reinforce fence.
40
Gross Tube Damage Gross tube damage that could compromise fence integrity
Criteria For Gross Tube Damage (Assumes Failed Batwing)
Location Unacceptable Acceptable Comments BW Penetration Less Cavity Peripheral Tube Severed Than -1/3 of the way Severed Tube is Weakness in Tube through the tube Defense Line Penetrated By Batwing BW Penetration Less -1/3 of the way through the Cavity Peripheral -1/3 of the way Than -1/3,of the way tube does not result in loss of through the tube through the tube cable function.
Cavity Peripheral Total Through Tube Tube-Double Sided section Wear greater Less Than -1/3 Through This value is the summation of than -1/3 of way total Tube Wear wear on both sides of the tube through tube diameter Interior Tube From Collapsed Or Visibly No visible.distortion Collapsed Tube w/o Cable is Cavity Distorted Tube potentially unacceptable Visible Thru Wall Tube Visible Thru Wall Tube Td From InteriorInterior Tube Fm Wear than that Wr greateraterantt .Wear less than that found Unexpected wear condition Cavity found in adjacent in adjacent peripheral tube peripheral tube 42
Criteria For Gross Batwing Induced Tube Prying Action (Assumes Failed Batwing)
Location Unacceptable Acceptable Comments Tube Spacing 1/3 tube diameter criteria is developed from greater than -1/3 Tube Spacing less than 140 mil fluid force load displacement plus Cavity tube diameter -1/3 tube diameter 116 mil original gap. Adjacent batwings Caviydameer tbe -/3 ube iamter must be examined to determine if tube Peripheral between adjacent between adjacent tube expein ed t prying force Tubes tube columns columns viewed along experienced significant prying forces or if the source of the abnormal spacing is due viewed along batwing to plastic deformation of a worn adjacent batwing batwing.
Tube! Unworn Tube/ Unworn batwing This equates to about 140 mil gap plus 116 Cavity Peripheral batwing gap greater than -1.5 gap less than -1.5 times mil original gap. Nominal Tube to Batwing Pperl gatierthikne -1 . thickness of nominal Clearance is 0.026 inch (0.013 inch on each Tube times thickness of batwing side).
nominal batwing Any Location Tube To Tube (Except Col Contact At See Above This indicates that large tube displacements 84/85 in SG Vertical Tube are occurring in the SG.
- 32) Section Distorted batwing observed in This indicates that large tube displacements Bundle innermost portion Undistorted batwings Location Loainof p tube bundle are occurring in the SG.
43
Foreign Object Search and Retrieval Contingencies (Chart IV)
- Large mass foreign objects are present
- Indicated by visible large loose batwing segment
- Contingency is to evaluate and if needed remove the part and install a new 6" access port to retrieve using special tooling
- Loose part with new visible wear scar on an active tube
" Indicated by visual scar on an active tube and comparison with as-left video and eddy current inspection from RF14.
- Contingency is to remove accessible parts and perform Plus Point test of affected tube and surrounding open tubes to determine depth of wear scar.
44
Stay Cavity Inspection Contingencies (Chart II)
Gross tube deformation is identified 0 Indicated by irregular tube spacing, tube dislocation, through-wall wear greater than one-third of the tube.
- Contingency is to bobbin test 5 open tubes per column closest to the damage and plus point identified wear. If stabilized tube, evaluate and determine whether needed to deplug and stabilize next tube in column to reinforce fence.
- Batwing at column 84/85 cold leg has dropped
° Indicated by visual extrusion beyond the 7th eggcrate and comparison with as-left video from RF14.
- If above the ~6 th eggcrate, contingency is to ECT open adjacent tubes to locate the displaced batwing and hydraulically expand selected tubes to capture and restrain the batwing.
If below the " 6 th eggcrate, contingency is to install a new 6" access port to retrieve using special tooling.
45
No Batwing Movement No Action 46
.:Moderate. Batwing Movement
.Batwi g Stabi ization 1 ~
F-on Fo.ces -e C~t rotte *Ot--g ony F-ee F-0 PF14 positio..
As ce,-el o. grolty ,s bove p.vot pOor. ,*w-9 ShceS 01059 the contoct r-ests c,'eoteO points 0100 1ne by 06 pPtol e~gc,orte egg-otes. D-e tore.-,gth toe I oter et', F botlct 47
Large Batwin--
Access P.ort to RE 48
,Iopment
- Substantially improved tooling has been developed to facilitate contingency plans
- Batwing cutting tool is different from previously discussed
- Diamond wire mockup tests were unsuccessful
- Versatile hydraulic tool developed 49
.,.ml
- -.tri e\
.~i.
4 I Delivery tool will have -150° range of motion V I .1
- 1 Ii A{
Multiple end effectors can be used with this delivery tool Air Gripper jf I£j .1;
- 1 1
...*::...:;*
50
Batwing GuttirngT
... ;."*... . * * :.. A..
Solin StayCav43ty Mbcku2p . ...
.i,.. ..**.*.
- !:.::.:& . ' . :....*i.*** I! '
. ,....*: . * ..:/* -.,!
.;* " " " : "
..:... v
. .,
" *° !:I : i * ; * .*;
.1i*,' ..'. . ;a
- ::,ii *::
,*:: ...
S i..t 7, ...
- wit * * ::L ,*,. .*. ..:::* : *
- .. ..
t
.... 4,**, 51 K.. I
Access Hoe Cons~t~raints~
This image is of the handhole showing the tubelane with the center tie rods in place The center tie rods sleeves are 1.125" and the tubelane is 4.25",
leaving 1.56" on either side I
52
0!*:;*k* ,..'. ! L .".. .
/I &-%I 1
-up*:*"i*'* Lower
- ...*.,/.* *.
. @f* i*.
Model showing the center stay area with stay cap and blow down Center tie rods Stay cap Blow down pipe 53
Mid-Cycle Contingencies and Criteria Summary
- Secondary inspections (Upper, Lower and FOSAR) will verify that the critical variables used for the repair plan and operational assessment are met
- The potential outcomes of each secondary inspection activity have been evaluated and appropriate contingencies planning has been taken
- A comprehensive decision flow chart has been prepared 54
Mid-Cycle Communication Plan Bob Murillo 55
SG Mid-Cycle Communication Plan
" Licensing Manager will be focal point for communications with NRC
" Pre-established communication plan
- NRR and Region IV management points of contact
- NRC Resident Inspector will be briefed daily Teleconference with NRR/Region IV, as needed
- Review of inspection results
- Review of contingency decision making
- Expansion of inspection scope
- Finding of unexpected results NRC requested photographs or video media will be made available via Licensing Manager 56
Summary and Q&A Joe Kowalewski 57
Conclusions
- Continued focus on safe operation
- Continued conservative approach to evaluation and mitigation of batwing condition utilizing defense in depth strategy
" Continue the operational monitoring, heightened awareness and conservative action limits
° Visual inspections planned for the mid-cycle outage will identify any unforeseen extent of condition or unforeseen change in the critical variables that were the basis for the repair plan and operational assessment
" Appropriate contingency actions are planned with pre-determined decision criteria to facilitate decision making for any unexpected findings.
- Communication strategy is in place for prompt information exchange 58