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Category:Letter
MONTHYEARIR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000261/20240112024-06-0303 June 2024 Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping IR 05000261/20240012024-05-0909 May 2024 Integrated Inspection Report 05000261/2024001 IR 05000261/20240102024-04-30030 April 2024 Biennial Problem Identification and Resolution Inspection Report 05000261/2024010 IR 05000261/20230062024-02-28028 February 2024 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 - Report 05000261-2023006 IR 05000261/20243012024-02-0606 February 2024 – Notification of Licensed Operator Initial Examination 05000261/2024301 IR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 IR 05000261/20220022022-08-0909 August 2022 Integrated Inspection Report 05000261 2022002, 07200060 2022001 and Exercise of Enforcement Discretion ML22213A0682022-08-0505 August 2022 Request for Withholding Information from Public Disclosure for H. B. Robinson Steam Electric Plant, Unit 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves IR 05000261/20220112022-07-19019 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000261/2022011 2024-08-01
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24143A0612024-05-22022 May 2024 NRC Presentation Slides for Topical Reports to Support SLR (5-22-24 Public Meeting) V2 ML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22007A2592022-02-0202 February 2022 Presubmittal Licensee Presentation for TS 3.5.3 PIV Testing LAR ML21167A0852021-06-24024 June 2021 Licensee Presentation for Robinson Pre-submittal Meeting TSTF-577 ML21174A3212021-06-24024 June 2021 Licensee Presentation for Robinson Presubmittal Meeting TSTF 577, Rev. 1 ML21105A7522021-04-15015 April 2021 2020 Robinson - EOC Presentation Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML18144A0632018-05-24024 May 2018 Summary of Meeting Concerning Annual Assessment of H.B. Robinson Steam Electric Plant Unit 2 for Period of January 1, 2017 - December 31, 2017 ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17244A2272017-09-0707 September 2017 Duke Energy Presentation - H.B. Robinson 2017-09-07 Pre-sub Transmission Upgrade Meeting ML16112A2932016-05-0202 May 2016 05/02/2016 Presentation for Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson And Shearon Harris Plants (CAC Nos. MF7443 And MF7444) RA-15-0041, Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted)2015-09-18018 September 2015 Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted) ML15231A6062015-08-19019 August 2015 Duke Energy Presentation - Robinson Nuclear Plant Transmission Upgrade Pre-submittal Meeting 08-26-2015 - MF6477 ML15125A4382015-05-0505 May 2015 Public Meeting Summary - 2014 Annual Assessment Public Meeting Regarding H.B. Robinson Steam Electric Plant ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson ML14181A0782014-06-30030 June 2014 June 30 NRC Slides for Public Meeting with Duke - NTTF 2.1 - Seismic Reevaluation - GMRS ML14154A0932014-06-0303 June 2014 May 28, 2014, Summary of Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13238A0542013-08-23023 August 2013 Meeting Summary - Category 1 Public Meeting Regulatory Conference, H.B. Robinson Steam Electric Plant, Docket No. 50-261 ML13127A0802013-04-18018 April 2013 Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP ML12331A1782012-11-26026 November 2012 Meeting Slides Re GSI-191 Strainer Fiber Bypass Test Plan Slides for H. B. Robinson Unit 2 ML12206A3252012-08-0707 August 2012 G20120513/EDATS: OEDO-2012-0436 - Briefing Book for Meeting with Duke Energy on August 7, 2012 ML12188A0712012-07-11011 July 2012 G20120473/ EDATS: OEDO-2012-0404 - Briefing Book - Briefing Package for Meeting with Duke Energy on July 11, 2012 ML12107A3552012-04-16016 April 2012 4/11/2012 Summary of Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML1124200662011-08-30030 August 2011 Meeting Summary - Robinson - NRC Slides ML1124200682011-08-30030 August 2011 Meeting Summary - Robinson - Progress Energy Slides ML1123603572011-08-24024 August 2011 Meeting Slides ML1123601792011-08-24024 August 2011 8/25/2011- Robinson Nuclear Plant Regulatory Performance Meeting Slides ML12083A0492011-07-20020 July 2011 Meeting Slides - Meeting with Carolina Power & Light Company to Discuss the H. B. Robinson Steam Electric Plant, Unit 2 Performance Improvement Plant and New Management ML1113703442011-05-11011 May 2011 05/11/2011 Meeting Slides Regarding Strategic Plan ML1108909072011-03-30030 March 2011 Slides of Meeting Regarding H.B. Robinson Annual Assessment Meeting ML1108908992011-03-30030 March 2011 Attendance List of 03/24/11 Meeting Regarding Annual Assessment of H.B. Robinson Steam Electric Plant ML1013904942010-05-12012 May 2010 Event Review for Robinson - Slides ML1011703342010-04-27027 April 2010 Summary of Category 1 Public Meeting with Carolina Power and Light Company Regarding NRC Reactor Oversight Process Annual Assessment H.B. Robinson Steam Electric Plant, Unit 2 ML1006203162010-03-10010 March 2010 Summary of Meeting with Progress Energy Carolina, Inc. to Discuss Issues Identified During NRC Staff'S Review of H. B. Robinson Steam Electric Plant, Unit 2, Generic Letter 2004-02 Supplemental Responses ML0912706522009-05-0606 May 2009 Summary of Category 1 Public Meeting Discussed NRC Reactor Oversight Process Annual Assessment of H. B. Robinson, Unit 2 ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0813706302008-05-0707 May 2008 Slides from H. B. Robinson Meeting Re. Robinson Steam Electric Plant Annual Assessment Meeting Reactor Oversight Program - Cy 2007 ML0722100412007-07-26026 July 2007 Meeting Slides NRC Region Meeting Robinson Nuclear Plant. ML0716505352007-05-21021 May 2007 Enclosure - Slides for NRC CY2006 Annual Assessment Meeting ML0611402602006-04-0404 April 2006 Public Meeting Slides - Category One Management Meeting H. B. Robinson, Unit 2 ML0615301932006-03-27027 March 2006 NFPA 805 Pilot Observation Visit Trip Report - March 2006 - Handouts ML0523604402005-08-11011 August 2005 Attachment 4 - Progress Energy Slides ML0511004362005-03-24024 March 2005 NRC CY2004 Annual Assessment Meeting - Robinson - Hartsville, South Carolina, March 24, 2005 ML0436402692004-12-0909 December 2004 Progress Energy, Meeting Briefing of 12/9/04, Fire Protection Program ML0901504242004-08-25025 August 2004 Progress Energy Carolinas, Inc., Handouts for the Brunswick and H.B. Robinson NPP Tours During the Shearon Harris Scol Environmental Site Audit of Alternative Sites ML0410600042004-03-30030 March 2004 Presentation of NRC CY2003 Annual Assessment Meeting for H.B. Robinson 2024-05-22
[Table view] Category:Meeting Summary
MONTHYEARML24165A2362024-06-21021 June 2024 Duke Robinson Technical Report 5-22-24 Public Meeting Summary ML24124A0342024-05-0101 May 2024 Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris ML23129A0012023-06-26026 June 2023 May 2, 2023, Summary of Meeting Duke Energy to Discuss an H. B. Robinson Steam Electric Plant, Unit No. 2 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High ML22262A2882022-10-0303 October 2022 Summary of September 14, 2022, Observation Public Meeting with Duke Energy Progress, LLC to Discuss a Planned TSTF-577, Rev. 1, License Amendment Request Supplement for H. B. Robinson Steam Electric Plant, Unit No. 2 ML22174A2872022-07-14014 July 2022 Summary of Pre-Submittal Meeting with Duke Energy Progress, LLC to Discuss a Potential License Amendment Request Proposed Technical Specification 3.3.2 for the H. B. Robinson Steam Electric Plant, Unit No. 2 ML22166A0182022-07-0707 July 2022 Summary of June 13, 2022, Closed Meeting with Duke Energy Progress, Llc to Discuss Licensee Responses Provided to a Request for Additional Information Associated with a License Amendment Request to Adopt Technical Specifications Task Force ML22131A3802022-05-12012 May 2022 Public Meeting Summary - 2021 Annual Assessment Meeting Regarding the H. B. Robinson Steam Electric Plant, Docket No. 50-261, Meeting Number 20210460 ML22129A0062022-05-10010 May 2022 Summary of April 20, 2022, Meeting with Duke Energy Progress, LLC, to Discuss Proposed License Amendment Request to Revise Reactor Coolant System Pressure Isolation Valve Operational Leakage Surveillance Requirement Frequency (L-2022-LRM 00 ML22091A2692022-04-19019 April 2022 Summary of March 30, 2022, Pre-Submittal Meeting with Duke Energy Progress, LLC to Discuss a Potential License Amendment Request Surveillance Requirements 3.8.1.16 for H. B. Robinson Steam Electric Plant, Unit 2 ML21341A5542021-12-29029 December 2021 Summary of November 29, 2021, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Planned License Amendment Request to Relocate ML21182A2202021-07-0909 July 2021 Summary of June 24, 2021, Meeting with Duke Energy Progress, LLC, Regarding a Proposed Amendment Concerning TSTF-577, Revised Frequencies for Steam Generator Frequencies for Steam Generator Tube Inspections, for the H. B. Robinson Steam Ele ML21068A4172021-03-17017 March 2021 Summary of Meeting with Duke Energy Progress, LLC, Regarding a Proposed Relief Request Concerning Containment Inspections of Liners and Moisture Barriers for the H. B. Robinson Steam Electric Plant, Unit 2 ML20141L6282020-05-20020 May 2020 EOC Meeting Summary ML19331A8062020-01-29029 January 2020 Summary of November 13, 2019 Closed Meeting with Duke Energy Carolinas, LLC and Duke Energy Progress, LLC, to Discuss Security-Related Information for Its Licensed Facilities ML19220A6702019-08-26026 August 2019 Summary of August 7, 2019, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Proposed License Amendment Request for a Common Emergency Plan ML19123A1592019-05-0101 May 2019 Summary of Public Meeting with H. B. Robinson Steam Electric Plant, to Provide Opportunities to Discuss the Annual Assessment of the H.B Robison Steam Electric Plant with the Public for Period of January 1, 2018 - December 31, 2018 ML19087A0622019-04-11011 April 2019 Summary of March 25, 2019, Public Teleconference with Duke Energy to Discuss the Request for Additional Information Response Regarding the Proposed Alternative to the Depth Sizing Qualification Requirement (Duke Energy Fleet Relief Request ML18144A0632018-05-24024 May 2018 Summary of Meeting Concerning Annual Assessment of H.B. Robinson Steam Electric Plant Unit 2 for Period of January 1, 2017 - December 31, 2017 ML17340A1302017-12-22022 December 2017 Summary of November 29, 2017, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Requests to Implement the Requirement of 10 CFR 50.69 at Brunswick, Shearon Harris, and H. B. Robinson ML17254A3492017-09-19019 September 2017 Summary of Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request Regarding a Transmission Upgrade at the H. B. Robinson Steam Electric Plant Unit No. 2 ML17223A1212017-08-17017 August 2017 Summary of August 3, 2017, Meeting with Duke Energy Progress, LLC on Proposed License Amendment Request to Implement Fuel Reload Design Methodology Reports for Shearon Harris and H. B. Robinson ML17097A2492017-04-0606 April 2017 Public Meeting Summary, 2016 Annual Assessment Public Meeting Regarding H.B. Robinson Steam Electric Plant, Docket No. 50-261 ML16235A2382016-10-17017 October 2016 Summary of the July 12-13, 2016 Audit Supporting the U.S. Nuclear Regulatory Commission Review of DPC-NE-1008-P, Nuclear Design Methodology Using CASMO-5/SIMULATE-3 for Westinghouse Reactors ML16123A0312016-05-26026 May 2016 Summary of Meeting with Duke Energy Progress, Inc. to Discuss a Proposed License Amendment Requests Regarding a 24 Month Fuel Cycle and an Alternative Source Term for Robinson, Unit No. 2 ML16123A0362016-05-0505 May 2016 Summary of the H.B. Robinson Steam Electric Plant, Unit 2 - February 9-10, 2016 Audit Associated With License Amendment Request to Transition to the National Fire Protection Association 805 Standard (CAC No. MF2746) ML16034A5242016-03-11011 March 2016 Summary of February 1, 2016, Pre-submittal Meeting with Duke Energy Regarding Consolidation of Emergency Operations Facilities ML15343A0712015-12-23023 December 2015 September 22-26, 2014, Summary of H. B. Robinson Steam Electric Plant, Unit 2 - Audit Associated with License Amendment Request to Transition to the National Fire Protection Association 805 Standard ML15280A2532015-11-25025 November 2015 Summary of Mtg. with Duke Energy Progress Inc. to Discuss Fuel Reload Design Methodology Reports & Proposed License Amendment Request Shearon Harris Nuclear Power Plant Unit 1 and H.B. Robinson Steam Electric Plant Unit No. 2 (MF6701/MF6702 ML15288A1312015-11-17017 November 2015 Summary of Meeting with Duke Energy Progress, Inc. to Discuss H. B. Robinson Steam Electric Plant Unit No. 2 - Proposed License Amendment Request Transmission Upgrades ML15281A1982015-11-10010 November 2015 Summary of Meeting with Duke Energy Progress Inc., to Discuss the H. B. Robinson Steam Electric Plant Unit No. 2, License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15117A5812015-05-0606 May 2015 April 14, 2015, Summary of Public Meeting on Calculation of Risk for NFPA-805 Fire Areas Crediting Control Room Abandonment ML15125A4382015-05-0505 May 2015 Public Meeting Summary - 2014 Annual Assessment Public Meeting Regarding H.B. Robinson Steam Electric Plant ML15068A3492015-03-18018 March 2015 Summary of March 4, 2015, Meeting with Duke Energy Progress, Inc., Regarding Pre-Submittal Meeting for 24-Month Fuel Cycle Proposed License Amendment Request ML14210A0502014-07-30030 July 2014 June 30, 2014, Summary of the Category 1 Public Meeting with Duke Energy Progress Inc. to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14154A0932014-06-0303 June 2014 May 28, 2014, Summary of Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML14112A4712014-05-0202 May 2014 Conference Call Summary - Regarding the Spring 2014 Steam Generator Inspections During a Forced Outage ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13238A0542013-08-23023 August 2013 Meeting Summary - Category 1 Public Meeting Regulatory Conference, H.B. Robinson Steam Electric Plant, Docket No. 50-261 ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop ML13155A1052013-06-12012 June 2013 May 2, 2013, Summary of Meeting with Duke Energy Concerning the Relocation of the Emergency Operating Facilities ML13150A0742013-05-29029 May 2013 Meeting Summary - Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML13127A0502013-05-20020 May 2013 Summary of April 18, 2013, Meeting with Duke Energy Concerning the National Fire Protection Association (NFPA) 805: Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML12332A1932012-12-13013 December 2012 Summary of Public Meeting with Duke Energy Concerning GL 2004-02 and NRC Staff Review of Draft Proposed Strainer Fiber Bypass Test Plan Re H. B. Robinson Steam Electric Plant, Unit 2 ML12107A3552012-04-16016 April 2012 4/11/2012 Summary of Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML1113703382011-05-17017 May 2011 Meeting Summary Letter Regarding Performance Improvement Plan ML11116A0202011-05-12012 May 2011 April 12, 2011, Summary of Pre-Application Meeting with Carolina Power & Light Company and Florida Power Corporation, on Brunswick, Units 1 & 2, Crystal River, Unit 3, and H. B. Robinson, Unit 2 ML1023804682010-08-26026 August 2010 08/18/10 Summary of Meeting NRC Initial Exam Writer'S Workshop ML1015803032010-06-0707 June 2010 Summary of Meeting with Augmented Inspection Team to Discuss the Results of an Augmented Inspection at the H.B. Robinson Team Electric Plant ML1013904872010-05-19019 May 2010 Summary of Category 1 Public Meeting with Carolina Power & Light Company H. B. Robinson Steam Electric Plant Fire Event on March 28, 2010 ML1011703342010-04-27027 April 2010 Summary of Category 1 Public Meeting with Carolina Power and Light Company Regarding NRC Reactor Oversight Process Annual Assessment H.B. Robinson Steam Electric Plant, Unit 2 2024-06-21
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24143A0612024-05-22022 May 2024 NRC Presentation Slides for Topical Reports to Support SLR (5-22-24 Public Meeting) V2 ML24136A2482024-05-22022 May 2024 NRC Presentation Slides for Topical Reports to Support SLR (5-22-24 Public Meeting) ML24134A0242024-05-22022 May 2024 Duke Presentation Slides Robinson-2 5-22-24 (Trs) ML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML23087A2922023-04-12012 April 2023 2022 Annual Assessment Meeting ML22301A1662022-09-29029 September 2022 Presentation 4 - Recent Biennial PI&R Team Inspection Insights ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22257A2392022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22151A2652022-05-31031 May 2022 Presubmittal Licensee Presentation for 3.3.2 ESFAS Proposed LAR ML22109A2122022-04-20020 April 2022 Duke Energy Pre-Submittal Public April 20, 2022, Meeting Presentation ML22083A1072022-03-30030 March 2022 Presubmittal Licensee Presentation for SR 3.8.1.16 Proposed License Amendment Request (EPID L-2022-LRM-0021) (Slides) ML22007A2592022-02-0202 February 2022 Presubmittal Licensee Presentation for TS 3.5.3 PIV Testing LAR ML21322A3262021-11-29029 November 2021 Duke Energy November 29, 2021 Pre-Submittal Public Meeting Slides for EOF Relocation Licensing Amendment Request ML21174A3212021-06-24024 June 2021 Licensee Presentation for Robinson Presubmittal Meeting TSTF 577, Rev. 1 ML21167A0852021-06-24024 June 2021 Licensee Presentation for Robinson Pre-submittal Meeting TSTF-577 ML21105A7522021-04-15015 April 2021 2020 Robinson - EOC Presentation Slides ML21053A0472021-02-25025 February 2021 Duke Energy Pre-Submittal Meeting - February 25, 2021 - H. B. Robinson 3rd Interval Containment ISI Relief Request ML20132A0002020-05-11011 May 2020 EOC Presentation ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17244A2272017-09-0707 September 2017 Duke Energy Presentation - H.B. Robinson 2017-09-07 Pre-sub Transmission Upgrade Meeting ML17200C7802017-07-19019 July 2017 Duke Energy Pre-submittal Meeting Presentation, August 3, 2017, Harris and Robinson License Amendment Request to Support the Transition to Duke Non-LOCA Analysis Methods, MF9824, MF9825 ML16112A2932016-05-0202 May 2016 05/02/2016 Presentation for Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson And Shearon Harris Plants (CAC Nos. MF7443 And MF7444) ML16105A3342016-04-20020 April 2016 H. B. Robinson Steam Electric Plant, Unit 2 - April 20, 2016, Duke Energy Presentation for 24-Month Fuel Cycle Pre-submittal Meeting (CAC No. MF7503) ML15231A6062015-08-19019 August 2015 Duke Energy Presentation - Robinson Nuclear Plant Transmission Upgrade Pre-submittal Meeting 08-26-2015 - MF6477 ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson ML14181A0782014-06-30030 June 2014 June 30 NRC Slides for Public Meeting with Duke - NTTF 2.1 - Seismic Reevaluation - GMRS ML14154A0932014-06-0303 June 2014 May 28, 2014, Summary of Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13238A0542013-08-23023 August 2013 Meeting Summary - Category 1 Public Meeting Regulatory Conference, H.B. Robinson Steam Electric Plant, Docket No. 50-261 ML13150A0742013-05-29029 May 2013 Meeting Summary - Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML13127A0802013-04-18018 April 2013 Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP ML12107A3552012-04-16016 April 2012 4/11/2012 Summary of Category 1 Public Meeting - Annual Assessment of H.B. Robinson Steam Electric Plant ML1124200662011-08-30030 August 2011 Meeting Summary - Robinson - NRC Slides ML1124200682011-08-30030 August 2011 Meeting Summary - Robinson - Progress Energy Slides ML1123601792011-08-24024 August 2011 8/25/2011- Robinson Nuclear Plant Regulatory Performance Meeting Slides ML1123603572011-08-24024 August 2011 Meeting Slides ML12083A0492011-07-20020 July 2011 Meeting Slides - Meeting with Carolina Power & Light Company to Discuss the H. B. Robinson Steam Electric Plant, Unit 2 Performance Improvement Plant and New Management ML1113703442011-05-11011 May 2011 05/11/2011 Meeting Slides Regarding Strategic Plan ML11102A0052011-04-12012 April 2011 Progress Energy - Slides for NFPA 805 Pre-LAR Application Meeting April 12, 2011 ML1108909072011-03-30030 March 2011 Slides of Meeting Regarding H.B. Robinson Annual Assessment Meeting ML1032006182010-11-16016 November 2010 Public Meeting Summary - Category One - Regulatory and Enforcement Conference Meeting (Robinson) ML1013904942010-05-12012 May 2010 Event Review for Robinson - Slides ML1011703342010-04-27027 April 2010 Summary of Category 1 Public Meeting with Carolina Power and Light Company Regarding NRC Reactor Oversight Process Annual Assessment H.B. Robinson Steam Electric Plant, Unit 2 ML0912706522009-05-0606 May 2009 Summary of Category 1 Public Meeting Discussed NRC Reactor Oversight Process Annual Assessment of H. B. Robinson, Unit 2 ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0813706302008-05-0707 May 2008 Slides from H. B. Robinson Meeting Re. Robinson Steam Electric Plant Annual Assessment Meeting Reactor Oversight Program - Cy 2007 ML0722100412007-07-26026 July 2007 Meeting Slides NRC Region Meeting Robinson Nuclear Plant. 2024-05-22
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 August 23, 2013 EA-13-129 Mr. William R. Gideon Vice President Duke Energy H. B. Robinson Steam Electric Plant, Unit 2 3581 West Entrance Rd Hartsville, SC 29550
SUBJECT:
MEETING
SUMMARY
- CATEGORY 1 PUBLIC MEETING - REGULATORY CONFERENCE, H.B. ROBINSON STEAM ELECTRIC PLANT, DOCKET NO.
50-261
Dear MR. Gideon,
This refers to the meeting conducted at your request at the NRC Region II Office on August 19, 2013, at 10:30am, Eastern Time. The purpose of this Regulatory Conference was for you to present to the NRC your perspectives on the facts and assumptions used by the NRC to arrive at the finding and the significance stated in the Inspection Report (IR) 05000261/2013008. This meeting also provided you an opportunity to provide other information you believe the NRC should take into consideration before making an enforcement decision. Enclosed are a list of attendees (Enclosure 1) and the presentation handouts (Enclosure 2).
The topics discussed included Duke Energys position with regard to the preliminary White finding documented in IR 05000261/2013008. This preliminary White finding was associated with an apparent violation (AV) of 10 CFR 50.63, Loss of All Alternating Current Power, as a result of the licensees failure to inspect the dedicated shutdown diesel generator radiator fan belts in accordance with the vendors recommended maintenance guidelines. We will consider the information you provided prior to making an enforcement decision.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records (PARS) component of NRC's Agency-wide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).
W. Gideon 2 Should you have any questions concerning this conference, please contact me at 404.997.4645.
Sincerely,
/RA By James Dodson For/
George Hopper, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket No.: 50-261 License No.: DPR-23
Enclosures:
- 1. List of Attendee
- 2. Duke Energy Presentation Slides cc: Distribution via Listserv
___ML13238A054______ SUNSI REVIEW COMPLE FORM 665 ATTACHED OFFICE RII:DRP RII:DRP SIGNATURE /RA/ /RA/
NAME SHerrick JDodson DATE 8/20/2013 8/20/2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
W. Gideon 3 Letter to William R. Gideon from George Hopper dated August 23, 2013
SUBJECT:
MEETING
SUMMARY
- CATEGORY 1 PUBLIC MEETING - REGULATORY CONFERENCE, H.B. ROBINSON STEAM ELECTRIC PLANT, DOCKET NO.
50-261 DISTRIBUTION:
OEMAIL OEWEB Region II Regional Coordinator NRR Enforcement Coordinator Enforcement Officer and Regional Counsel, RII Public Affairs Officer, RII Chief, Resource Management Branch, RII Region II Administrator's Secretary DRP Division Secretary Region II Division Directors and Deputies Region II Receptionist Headquarters Operations Officer NRR DISP/PIPB (reactor cases)
L. Douglas, RII, EICS RIDSNRRDIRS RidsNrrPMRobinson Resource PUBLIC
List of Attendees NRC L. Wert, Deputy Regional Administrator, RII C. Evans, Regional Counsel, RII S. Sparks, Senior Enforcement Specialist, RII R. Croteau., Director, Division of Reactor Projects (DRP)
W. Jones, Deputy Director, DRP H. Christensen, Deputy Director, Division of Reactor Safety (DRS)
G. Hopper, Chief, DRP, Reactor Projects Branch (RPB) 4 C. Scott, Acting Senior Resident Inspector, Robinson, RII J. Hickey, Chief, Division of Fuel Facility Inspection, Fuel Facility Branch 2, RII J. Dodson, Senior Project Engineer, DRP, RPB 4 S. Herrick, Project Engineer, DRP, RPB 4 G. MacDonald, Senior Reactor Analyst, RII J. Circle, Senior Reliability and Risk Analyst, HQ Call-in attendees:
M. Halter, Office of Enforcement, HQ L. Casey, Office of Enforcement, HQ K. Ellis, Senior Resident Inspector, Robinson, RII DUKE / Robinson P. Gillespie, Senior Vice President Nuclear Operations R. Gideon, Site Vice President T. Cosgrove, Plant General Manager J. Kammer, Director, Engineering K. Holbrook, Manager, Operations D. Douglas, Manager, Maintenance B. Rishel, Manager, Probabilistic Risk Analysis J. McCrory, Senior Engineer, Probabilistic Risk Analysis R. Hightower, Supervisor, Licensing C. Nolan, Director, Corporate Regulatory Affairs Call-in attendee:
D. Cummings, Associate General Counsel Public (call-in)
R. Thomas S. Cownoley S. Threatt, State of SC T. McKinney, State of SC Enclosure 1
Robinson Nuclear Plant Dedicated Shutdown Diesel Fan Belt Performance Deficiency August 19, 2013 Regulatory Conference
Duke Participants
Preston Gillespie Senior Vice President, Nuclear Operations
Randy Gideon Site Vice President
Mike Glover Director, Site Operations
Tom Cosgrove Plant General Manager
Jim Kammer Director, Engineering
John Little Manager, Shift Operations
Donnie Douglas Manager, Maintenance
Bob Rishel Manager, Probabilistic Risk Analysis
Richard Hightower Supervisor, Licensing
Chris Nolan Director, Regulatory Affairs 2
Agenda
Opening Remarks R. Gideon
DSDG Design and Timeline J. Kammer
Operations Response J. Little
Maintenance Response D. Douglas
Significance Determination B. Rishel
Cause Analysis & Corrective Actions T. Cosgrove
Regulatory Perspective M. Glover
Closing Remarks P. Gillespie 3
Opening Remarks
Robinson agrees with the apparent violation described in the NRCs letter dated July 1, 2013
Robinson understands the importance of the Dedicated Shutdown Diesel-Generator (DSDG)
Performance did not meet our expectations for maintaining the DSDG
Root Cause Evaluation performed
Key drivers contained in the Probability Risk Assessment (PRA):
Mitigation measures to maintain secondary side cooling
High probability of success for fan belt replacement
Postulated damage from arc faulting in 480V cabinets
Duke Energys analysis concludes that the Finding is of very low safety significance 4
Dedicated Shutdown Diesel Generator Design and Timeline Jim Kammer Robinson Engineering Director 5
Robinson Design Topics
DSDG Design
Relevant Robinson Design Features
DSDG Belt Failure Timeline
Postulated Events affected by DSDG Belt Failure
Overall Postulated Event Timeline 6
DSDG Design
DSDG installed in 1981
The DSDG provides a source of electrical power to bring the plant safely to a hot shutdown condition in the event of a fire
DSDG automatically provides an emergency source of electrical power in the event of a simultaneous loss of all off-site power and both EDGs Fan Belt Guard 7
Design Features
Emergency AC Power
480V Emergency Power System versus more typical 4160V systems
Amptectors are installed on Emergency Bus E1 and E2 Supply Breakers
Spatial separation results in Emergency Bus E1 High Energy Arc Fault (HEAF) not directly impacting Emergency Bus E2 and vice versa
In the Cable Spread and Emergency Switchgear Rooms, fire retardant coating is applied to cables in tray that are not flame spread rated
Instrumentation
Instrumentation required for Operators to assess and maintain secondary side heat removal does not rely on power from Dedicated Shutdown (DS) Bus
Steam Driven Auxiliary Feedwater Pump flow indication does not rely on power from the DS Bus
Radio communications do not rely on power from the DS Bus 8
DSDG Belt Failure Timeline Started DSDG Closed DSDG DSDG unloaded breaker automatic successfully from the 52/32B and shutdown on tested per DSDG loaded the high OST-910 enclosure per DSDG temperature monthly OST-910 Aug 28 Oct 2 Oct 2 Oct 2 1808 1623 1648 1703 9
Postulated Fire Events Affected by DSDG Belt Failure
Postulated large fire affecting onsite power distribution
Dominates both Duke and NRC Risk Significance Analysis
Postulated loss of Offsite and Emergency AC power internal to power block only
Support facilities would continue to receive AC power from retail distribution system 10
Postulated Fire Event Timeline 0 Minutes 78 Minutes 150 Minutes 255 Minutes Core Inventory Makeup Operations Event Initiation Required Recovery Normal DS Indications DS Battery Depleted Maintenance Repair of DSDG Radiator Fan Belt 11
Operations Response John Little Robinson Manager - Shift Operations 12
Operations Response - Overview
Operators would maintain adequate heat sink capability for core decay heat removal
Procedural Direction
Training
Periodic Examinations
Operator Fundamentals
Operators would respond to the fire using AOP-041, Response to a Fire Event and DSP-001, Alternate Shutdown Diagnostic
Based on postulated fire location or procedural progression, both emergency buses and offsite power are assumed to be unavailable 13
Operations Response - Overview
Depending on the limiting event, Operators would respond with
DSP-002, Dedicated Shutdown Procedure - Hot Shutdown Using the Dedicated/Alternate Shutdown System
EPP-1, End Path Procedure - Loss of All AC Power
For the purposes of this discussion, DSP-002 response is more limiting
Cooldown rate
DSP-002 - 25°F/hr
EPP 100°F/hr
DSP-002 exposes RCP seals to elevated temperature for a longer period of time
Other factors
Requires control of the plant from local control stations
Communications and direction via radio 14
Operations Response - Procedural Requirements
Operators will maintain Auxiliary Feedwater flow ensuring the critical safety function for heat sink - 300 gpm Auxiliary Feedwater (AFW) flow or minimum of 8% SG narrow range (60% wide range) level
Procedure steps direct maintaining heat sink early in response:
EOP-E-0, Reactor Trip or Safety Injection, steps 6 through 8 (prior to entry into DSP-002)
EPP-1, step 7
DSP-002, Attachment 1, Turbine Building Operator, steps 6 and 7 15
Operations Response - Anticipating Plant Response
Stable cooldown rate with valve position procedurally established via DSP-002 prior to DS battery depletion
DSP-002 implements DSP-007, Cold Shutdown Using DS System
DS Battery Depletion occurs in One Hour
Included in procedural basis in multiple procedures
EOP-E-0
OP-602, Dedicated Shutdown System
Operators would expect effects of depletion of DS battery after trip of the DSDG and would have one hour to prepare
Based on related procedures
Feedwater flow will continue for heat sink 16
Operations Response - Reinforced by Training
Dedicated Shutdown (DS) Procedural Strategy included as part of Operator Initial Training Curriculum
Continuing Training Backbone
Prior to DSDG Belt Failure
DSP-002, last completed August 2011
EPP-1, last completed June 2012 17
Operations Response - Reinforced by Training
Importance of DS strategy including DSDG reflected by frequency they appear in Licensed Operator Job Performance Measure (JPM) annual exams:
2009 - Local SG PORV control
2009 - Energizing DS Bus using DSDG per DSP-002
2010 - Deenergizing Emergency Buses per DSP-002
2010 - Manual Start of the DSDG per EPP-1
2012 - Manual Start of DSDG per DSP-002 (after AUTO start mod)
2012 - Respond to a loss of all AC Power EPP-1 (AFW Flow)
2013 - Start CCW Pump A, Control Charging Pump A locally per DSP-002 18
DSP-002, Alternate Hot Shutdown System Procedure
Operations personnel proceed to the pre-arranged muster location 19
DSP-002, Alternate Hot Shutdown System Procedure
Radios, portable lights and controlled procedures maintained in the muster location
Radio communication between operators has been demonstrated
Channel 2 does not require use of repeater
Successfully Tested at NRC request - 2007 Triennial Fire Protection Inspection (IP 71111.05); from Muster Location to Charging pump room on channel 2 without need for repeater (11/07/07)
Functionality tested monthly per OST-639, Fire Equipment Inventory
Test successfully repeated on 08/07/13:
Muster location to Secondary Control Panel, Charging Pump Room, and SI Pump Room
If Shift Manager goes to Work Control, communicates to Charging Pump Room via Secondary Control Panel Operator 20
Secondary Control Station
Operators control the plant at the secondary control station
Location where cooldown established
Natural circulation including subcooling checked at step 10 of DSP-002, Att. 1 21
AFW Flow Control Valves
Operators control AFW flow using valves adjacent to the control panel to maintain the secondary heat sink
A stable cooldown rate with associated valve position via DSP-002 would have been attained by the time of DS battery depletion 22
Indications Used for Control
Secondary Control Station - Multiple indications available at the start of the postulated scenario and for one hour on the DS batteries after DSDG trip
SG Level (all three SGs)
Pressurizer (PZR) Level
Pressurizer Pressure
Condensate Storage Tank Level
A RCS Cold Leg Temperature
A RCS Hot Leg Temperature
Indications remaining after battery depletion
AFW flow via FT-6416 - 1st level Turbine Building
SG Pressure - Secondary Control Station 23
Secondary Control Station Operators use the indication of SG pressure (left) and the curve from DSP-002 (right) to correlate and control RCS cold leg temperature and ensure decay heat removal
Indications of pressure for all three steam generators would remain available
purely mechanical, no electrical power necessary
SG level indication not necessary FT-6416 - Local Feed Flow indication, first level turbine building (center), remains available, electrical power not required 24
Response to DSDG High Temperature Trip
Operators will maintain feedwater flow ensuring critical safety function of heat sink for decay heat removal
AFW flow procedurally driven to 300 gpm minimum
SG levels procedurally established and maintained between 60 and 68%
Stable cooldown rate of 25°F/hour after entry into DSP-002
Operator have the procedures, training, indications, and fundamental knowledge to successfully maintain decay heat removal
Performance of DSP-002 provides a success path
Flow rates to the SG are relatively stable when DS Battery is depleted
Vapor volume of SGs sufficient to prevent overfill after loss of level indication
SG Overfill will not occur in the postulated scenario 25
Operations Success Credit
Operator actions will succeed
Procedures direct continued flow to the steam generators
Available indications will be used to ensure SGs remain viable as a heat sink throughout the postulated scenario
Operator actions to maintain flow have been in progress prior to the loss of SG indication and will continue after the loss
Required only to continue feed flow and steaming monitoring SG pressure
Training and examinations reinforce continued flow to the steam generators
Effective Radio communications demonstrated 26
Maintenance Response Donnie Douglas Robinson Maintenance Manager 27
Maintenance Response
Personnel will respond to the ERO notification
Parts needed to repair the DSDG are readily obtained with or without computer resources or other support
Emergent Work Order using station process is designed for this type of situation
DSDG repair will succeed in required timeframe
Straightforward tasks
Simple, readily available tools 28
Maintenance Response Strategy to Postulated Fire Event 0 Minutes 18 Minutes 30 Minutes 60 Minutes 120 Minutes 150 Minutes Start of Belt Installation Core Inventory Makeup Team 1 Event Initiation ERO Notification Remove Guard Combined Team Personnel Arriving Travel to Site DSDG Trip Install Belts Team 2 Obtain Belts Operations Diagnosis of Trip 29
Maintenance Response Maintenance actions start to recover DSDG:
Within 60 minutes of the start of the scenario:
Maintenance personnel arrive on site
Missions to locate replacement belts and remove belt guard underway 30
Maintenance Response Within 120 minutes of the start of the scenario, Maintenance have obtained the replacement belts 31
Maintenance Response Within 120 minutes of the start of the scenario, Maintenance would have the guard off and the belts removed 32
Maintenance Success Credit
High Probability of Success
Emergency Response to fill two teams
Identifying/Acquiring Parts
core skill
trial scenarios
day and night acquisition
Emergent Work Order process practiced in Emergency drills/exercises
Belt replacement is a simple and frequent task
181 Work Order tasks performed over past 5 years associated with belt replacements or adjustments with one condition report for rework 33
Significance Determination Bob Rishel PRA Manager 34
Significance Determination - Overview
Robinson Basis for Very Low Safety Significance
- 1. Plant design and configuration of DS cables/HEAF sources make loss of DS Bus unlikely
Impact of 480V HEAF is smaller when compared to a 4160V HEAF
- 2. Recovery Credit
Operators establish/maintain SGs feed and cool down rates before DS battery depletion occurs
Operators maintain heat sink after DS battery depletion
Maintenance recovery of DSDG
The belt repair straightforward with simple tools 35
HEAFs in Robinson E1 Switchgear
Robinson 480V HEAF considerations
- 1. 480V E1 and E2 switchgear robust cabinet construction
Solid tops
Cabinets are secured with thread fasteners in corners
Supply breakers are in lower half of cabinet
Outgoing load breakers are protected with Amptectors
- 2. E2 cables and DS Bus cables are outside the Zone of Influence (ZOI) for E1 HEAF from supply breakers
- 3. No E2 damage from E1 HEAF
No loss of DS Bus due to E1 HEAF 36
Emergency Bus Configuration - Looking South Emergency Emergency Bus E1 Bus E2 37
Significance Determination Contributions
Robinson Incremental Conditional Core damage Probability (ICCDP) contribution from the E1 HEAF is <1E-08
This is based on:
E1 Switchgear energetic phase HEAF zone of influence does not cause a loss of DS Bus power or E2 Bus
Per NUREG/CR-6850 Appendix M and FAQ 06-0017, 480V HEAFs have not caused damage beyond the switchgear itself
FAQ 06-0017 limits 480V HEAFs to feeder breakers
The 480V HEAF ZOI is smaller than the NUREG/CR-6850 Appendix M for medium voltage switchgear 38
Significance Determination Recovery Credit
Full recovery credit (defined as 92.5%) should be applied
DSP-002 establishes initial success for SG feed with SDAFW
Maintaining feed leads to success
No diagnosis required by the operator
Stress - high
Complexity - nominal
Training - nominal
Procedures - available
Indications - available
Expansive time is available
Tech Support Center provides oversight
Fan Belt replacement is straightforward
Robinson ICCDP evaluation is approximately 6.5E-07 39
Causes and Corrective Actions Tom Cosgrove Robinson Plant Manager 40
Evaluation Results: Causes
Root Cause - A time based preventative maintenance basis prescribing fan belt replacement did not exist
Primary Contributing Causes
Belt Procedure steps not prescriptive
Degraded motor sheave condition
Contributing Causes
Did not exhibit the behaviors needed to achieve high standards of reliability and availability of the DSDG
Belt guard design precluded routine monitoring
Lack of maintenance rigor in use of vendor information (used qualitative vice quantitative inspection techniques) 41
Corrective Actions: Immediate / Interim
Immediate Actions Taken
Replaced the radiator fan belts
Modified the radiator fan belt guard
Interim Actions Taken
Implemented additional short term motor, fan and belt monitoring actions
Conducted leadership and maintenance briefs
Completed system expectation sessions with maintenance, engineering, work management, operations and station leadership 42
Corrective Actions: To Address Causes
Corrective Actions to Preclude Recurrence
Implemented a time based DSDG belt replacement frequency of 2 years
Other Key Corrective Actions to Address Causes
Replaced sheaves and modified the DSDG fan motor mounting
Revised maintenance procedures to include quantitative sheave exam, belt inspection, and tensioning criteria (Programmatic)
Integrated DSDG into the stations Reliability Improvement Plan (Organizational)
Conduct Training for Performance Improvement (Includes Continuing and Initial Training) 43
Corrective Actions: Extent of Condition
Emergency Diesel Generators (EDGs) A&B supply/exhaust fan belts replaced
Preventive Maintenance (PM) for EDGs supply/exhaust fan time based replacement
PM for time based replacement - Engine Driven Fire Pump/alternator
Security DG radiator fan and alternator drive belts replaced
PM for replacement of Instrument Air compressors A/B drive belts on 4 year frequency 44
Corrective Actions: Extent of Cause
Identify new PMs for belts
Flex equipment
4th Train AFW DG
Deep Well DG
Identify new PMs for elastomerics
AFW
Service Water
Fire Protection
CVCS
Expand scope of systems if 4 or more new PMs are needed
Single Failure study - DSDG and support systems 45
New Sheaves and Mounting System for DSDG Radiator Fan 46
Radiator Fan Belt Guard with New View Port View Port 47
Regulatory Perspectives Mike Glover Director - Site Operations 48
Regulatory Perspectives
Apparent violation of 10 CFR 50.63 (Blackout Rule) for failure to perform adequate preventative maintenance on the Dedicated shutdown Diesel Generator (DSDG) cooling system.
Robinson agrees with the Apparent Violation from the aspect that no time based replacement activity was in place for the DSDG radiator fan belts
Corrective Actions to restore compliance were completed on October 3, 2012
Comprehensive actions have been taken to prevent recurrence
Other corrective actions are taken or planned
In summary, despite the temporary loss of the DSDG, the combination of the above along with the other actions described in this presentation serve to ensure mitigation necessary to prevent core damage
Duke Energys analysis concludes that the Finding is of very low safety significance 49
Closing Remarks Preston Gillespie Senior Vice President, Nuclear Operations 50
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