Letter Sequence Meeting |
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EPID:L-2019-LRM-0079, SECY-18-0100: Annual Update Regarding the Integrated Strategy to Modernize the Nuclear Regulatory Commission'S Digital Instrumentation and Control Regulatory Infrastructure (Open) |
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MONTHYEARML18275A3272018-10-0909 October 2018 SECY-18-0100: Annual Update Regarding the Integrated Strategy to Modernize the Nuclear Regulatory Commission'S Digital Instrumentation and Control Regulatory Infrastructure Project stage: Request W3F1-2019-0034, Letter-of-Intent to Submit License Amendment Requesting Using Digital Instrumentation and Control Interim Staff Guidance-(ISG)-06, Revision 2 and Request for NRC Fee Waiver2019-05-16016 May 2019 Letter-of-Intent to Submit License Amendment Requesting Using Digital Instrumentation and Control Interim Staff Guidance-(ISG)-06, Revision 2 and Request for NRC Fee Waiver Project stage: Request 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 Project stage: Meeting ML19344D0362019-12-19019 December 2019 Request for Withholding Information from Public Disclosure Affidavit Dated December 4, 2019, Executed by Zachary S. Harper of Westinghouse Electric Company LLC Meeting Slides Project stage: Withholding Request Acceptance ML20013G2592020-02-0707 February 2020 Summary of December 11, 2019 Partially Closed Presubmittal Meeting with Entergy Operations, Inc., to Discuss the Effect of a Planned LAR for Digital Instrumentation and Control Modification on Accident Analyses at Waterford (L-2019-LRM-0079 Project stage: Meeting 2019-12-05
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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML23348A3572023-12-14014 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 ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary 2023-12-14
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23348A3572023-12-14014 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 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 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 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 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 2023-05-02
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Text
Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390 The balance of this letter may be considered nonproprietary upon removal of Attachment 3.
Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-464-3786 Paul Wood Manager, Regulatory Assurance Waterford 3 W3F1-2019-0082 December 5, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
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 at Waterford Steam Electric Station, Unit 3 (EPID L-2019-LRM-0079)
Waterford Steam Electric Station, Unit 3 NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38
Reference:
Meeting Notice, "Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification at Waterford Steam Electric Station, Unit 3 (EPID L-2019-LRM-0079), (ADAMS Accession No. ML19337B567), dated November 26, 2019 A partially closed meeting between Entergy Operations, Inc. (Entergy) and the U.S. Nuclear Regulatory Commission (NRC) staff is scheduled for December 11, 2019. The purpose of this meeting is to discuss one feature of a planned license amendment request to replace the Waterford 3 Core Protection Calculator and Control Element Assembly Calculator Systems in accordance with Digital Instrumentation and Control (DI&C) Interim Staff Guidance (ISG)
DI&C-ISG-06, Revision 2.
Attached to this letter are:
Presubmittal Meeting Slides, "Waterford Unit 3 CPC/CEAC Replacement License Amendment Request NRC Technical Meeting" [Westinghouse document WAAP-11619-NP (Non-Proprietary)] (Attachment 1).
W3F1-2019-0082 Page 2 of 3 Westinghouse Letter CAW-19-4979, Affidavit, Proprietary Information Notice, and Copyright Notice (Attachment 2).
Presubmittal Meeting Slides, "Waterford Unit 3 CPC/CEAC Replacement License Amendment Request NRC Technical Meeting" [Westinghouse document WAAP-11619-P (Proprietary)] (Attachment 3).
As Attachment 3 contains information proprietary to Westinghouse Electric Company LLC
("Westinghouse"), it is supported by an Affidavit signed by Westinghouse, the owner of the information. The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the Nuclear Regulatory Commission ("Commission") and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-19-4979 and should be addressed to Camille T. Zozula, Manager, Infrastructure & Facilities Licensing, Westinghouse Electric Company, 1000 Westinghouse Drive, Suite 165, Cranberry Township, Pennsylvania 16066.
This letter contains no new regulatory commitments.
If you have any questions or require additional information, please contact the Regulatory Assurance Manager, Paul Wood, at (504) 464-3786.
Respectfully, Paul Wood PW/mmz
W3F1-2019-0082 Page 3 of 3 Attachments: 1. Waterford Unit 3 CPC/CEAC Replacement License Amendment Request NRC Technical Meeting Slides [Westinghouse document WAAP-11619-NP (Non-Proprietary)]
- 2. Westinghouse Letter CAW-19-4979
- 3. Waterford Unit 3 CPC/CEAC Replacement License Amendment Request NRC Technical Meeting Slides [Westinghouse document WAAP-11619-P (Proprietary)])
cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford 3 NRC Project Manager - Waterford 3
Attachment 1 W3F1-2019-0082 Waterford Unit 3 CPC/CEAC Replacement License Amendment Request NRC Technical Meeting Slides
[Westinghouse document WAAP-11619-NP (Non-Proprietary)]
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Waterford Unit 3 CPC/CEAC Replacement License Amendment Request NRC Technical Meeting WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Participants Entergy/Westinghouse
- John Schrage, Senior Staff Engineer - Corporate Licensing, Entergy
- Jerry Holman, Safety Analysis SME, Entergy
- Amanda Charleroy, Westinghouse Manager, Transient Analysis, Westinghouse
- Kim Jones, Fellow Engineer, Transient Analysis, Westinghouse 2
WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Purpose and Goal of Meeting
Purpose:
Describe the approach that Entergy will utilize in the planned LAR for the Core Protection Calculator (CPC)/Control Element Assembly Calculator (CEAC) upgrade project to demonstrate that the calculated response times in the new CPCS design are bounded by the accident analysis (i.e., DI&C ISG-06, Revision 2, Item D.2.4.1).
- Meeting Goal: Inform NRC and obtain feedback concerning topics and information that should be included in LAR.
3 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Agenda
- Estimated Response Time Changes
- Estimated Impacts on Response Times
- Impact on Safety Analysis
- Qualitative Assessment Approach
WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Topic Statement
- Changes in calculated response times will impact the Waterford analyses of record (AOR).
- Revised analyses using the updated Common Q CPC response times will not be completed prior to LAR submittal in June 2020.
- This concludes the open portion of the meeting.
5 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved End of Open Portion 6
WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Estimated Response Time Changes
- The current Waterford 3 CPCS response time acceptance criteria is based on the calculated response time of legacy CPCS digital equipment, and not a bounding response time assumption.
- Common Q architectural changes will result in some response times for the new CPC system to be slightly different than those credited in Waterford-3 Safety Analysis Report (SAR) Chapter 15 Non-LOCA Safety Analyses 7
WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Conclusion
- The LAR will include a complete description of Waterford-specific calculated Common Q response times, and comparison with current response times.
- The LAR will include a complete description of qualitative approach used to evaluate the impact of the Common Q response times on the Chapter 15 non-LOCA transients that use a CPCS trip.
- The revised safety analyses will be completed prior to new fuel load, in accordance with 10 CFR 50.59 process. The 50.59 process will ensure the CPC response time changes remains within the existing operating margins.
8 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Estimated Response Time Changes (cont.)
- Common Q Architectural Changes o Single minicomputer to multiple Programmable Logic Controllers (PLCs) in a channel o Multiplication of CEACs from 2 to 8 o Conservative estimates in the Common Q calculation
- Gathering data from the additional components [increases] a,c the overall time required for CPC to complete its calculations and functions.
- The calculated response times will be determined as part of design process, with an expected completion date of January 2020.
- The expected Waterford-3 Common Q response times are based on the Palo Verde Nuclear Generation Stations (PVNGS) calculated Common Q values.
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
9 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Estimated Impact on Response Times Table 1 Examples Waterford-3 Current versus Expected Common Q Response Time Assumption
[ [
Waterford-3 Current Analysis Assumption Response Time msec ] a,c ] a,c Neutron Flux Power from Excore Detector 275 [ ]a,c [ ] a,c CEA Position - CPC 1343 [ ] a,c [ ] a,c Cold Leg Temperature (Tcold) 370 [ ] a,c [ ] a,c Hot Leg Temperature Variable Overpower Trip 370 [ ] a,c [ ] a,c Hot Leg Saturation Trip 2952 [ ] a,c [ ] a,c RCP Shaft Speed 232 [ ] a,c [ ] a,c Pressurizer Pressure 270 [ ] a,c [ ] a,c (a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
10 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Impacted Safety Analyses Table 2 Representative Chapter 15 Events Impacted
[
CPCS Auxiliary Trip SAR Chapter 15 Events Functions
] a,c HFP and HZP CEA Bank Withdrawal, Variable Overpower Trip Excess Load, [ ] a,c Pre-trip Steam Line Break, CEA Ejection Tcold Trip Asymmetric SG Transient [ ] a,c Loss of Forced Reactor Coolant Flow, RCP Shaft Speed Trip Single RCP Shaft Seizure/Sheared Shaft [ ] a,c Hot Leg Saturation Trip SG Tube Rupture [ ] a,c Pressurizer Pressure Letdown Line Break [ ] a,c Table 2 presents the impact on expected Common Q assumed response time assumptions for a representative set of Non-LOCA safety analyses from SAR Chapter 15.
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
11 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Qualitative Approach - Safety Analysis Impacts
- June 2020 CPC/CEAC LAR will utilize a qualitative approach, comparing the new calculated response times against the acceptance criteria, to demonstrate that Safety Analysis limits will not be exceeded with the calculated changes in response times.
- 2015 Waterford LAR requested approval to increase the average and slowest CEA drop time by 200 msec.
o The analytical approach that Entergy utilized to support the 200 msec delay in CEA drop time will be used to determine the impact of [increased] a,c CPC response times on affected safety analyses.
o The Common Q [increase] a,c in CPCS response times produces the same effect as the 2015 license amendment, but the [increases] a,c in response times are significantly smaller.
- There will be no changes to the accident analyses methodologies. The reload methodology will account for any changes in CPC response time by utilizing existing COLSS and CPC operating margins.
- The following tables demonstrate that after accounting for new response times, the Chapter 15 non-LOCA Safety Analysis will still meet the acceptance criteria.
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
12 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Qualitative Approach - Safety Analysis Impacts (cont.)
Table 3A Assessment Results for the Loss of Reactor Coolant Flow Parameter Previous Analysis Value for Expected Value Acceptance Analysis 200 msec Delay including Response Criteria Value Time of [ ] a,c DNBR 1.302 1.282(1) [ ] a,c 1.24 Peak Pressure, psia 2395 2415 [ ] a,c 2750
- 1) Value based on 200 msec change only; reported value is 1.293 which includes other conservatisms.
Table 3B Assessments Result for the Pre-Trip Steam Line Break Parameter Previous Analysis Value for Expected Value Acceptance Analysis 200 msec Delay including Response Criteria Value Time of [ ] a,c DNBR 1.428 1.365 [ ] a,c NA Fuel Failure, % 0 0 [ ] a,c 8 Table 3C Assessment Results for the Uncontrolled CEA Bank Withdrawal from HZP Parameter Previous Analysis Value for Expected Value Acceptance Analysis 200 msec Delay including Response Criteria Value Time of [ ] a,c DNBR 3.44 2.90 [ ] a,c 1.24 Full Power Seconds Limit, (sec) 1.35 1.49 [ ] a,c 2.53(1)
Fuel Centerline Temp. °F < 3500 < 3500 [ ] a,c < 4663(2)
- 1) The 2.53 seconds corresponds to a fuel centerline temperature of 3500 °F.
- 2) Actual Criteria for maximum allowed burnup.
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
13 WAAP-11619-NP
Westinghouse Non- Proprietary Class 3 © 2019 Westinghouse Electric Company LLC. All Rights Reserved Questions?
14 WAAP-11619-NP
Attachment 2 W3F1-2019-0082 Westinghouse Letter CAW-19-4979 As Attachment 3 contains information proprietary to Westinghouse Electric Company LLC, it is supported by an Affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations
Westinghouse Non-Proprietary Class 3 CAW-19-4979 Page 1 of 3 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
COUNTY OF BUTLER:
(1) I, Zachary S. Harper, have been specifically delegated and authorized to apply for withholding and execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse).
(2) I am requesting the proprietary portions of WAAP-11619-P be withheld from public disclosure under 10 CFR 2.390.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged, or as confidential commercial or financial information.
(4) Pursuant to 10 CFR 2.390, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse and is not customarily disclosed to the public.
(ii) Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for commercial power reactors without commensurate expenses.
Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
- This record was final approved on 12/4/2019 10:31:16 AM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 CAW-19-4979 Page 2 of 3 AFFIDAVIT (5) Westinghouse has policies in place to identify proprietary information. Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage (e.g., by optimization or improved marketability).
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(6) The attached documents are bracketed and marked to indicate the bases for withholding. The justification for withholding is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters
- This record was final approved on 12/4/2019 10:31:16 AM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 CA W-19-4979 Page 3 of 3 AFFIDAVIT refer to the types of information Westinghouse customarily holds in confidence identified in Sections (5)(a) through (f) of this Affidavit.
I declare that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
~lk=
Z~. f-farper, Manager Licensing Engineering
- This record was final approved on 12/4/2019 10:31:16 AM. (This statement was added by the PRIME system upon its validation)
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and non-proprietary versions of a document, furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.
In order to conform to the requirements of 10 CFR 2.390 of the Commissions regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted).
The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
- This record was final approved on 12/4/2019 10:31:16 AM. (This statement was added by the PRIME system upon its validation)