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EPID:L-2021-LRM-0017, 2 to Updated Final Safety Analysis Report, Chapter 3, Design Criteria - Structures, Components, Equipment and Systems (Open) |
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MONTHYEARML20309A7472020-10-0808 October 2020 2 to Updated Final Safety Analysis Report, Chapter 3, Design Criteria - Structures, Components, Equipment and Systems Project stage: Request PMNS20210152, Presubmittal Meeting with Duke Energy Progress, Llc. to Discuss a Future Relief Request Concerning Containment Metallic Liners and Moisture Barriers Inspection Requirements for the H. B. Robinson Steam Electric Plant, Unit No. 22021-02-11011 February 2021 Presubmittal Meeting with Duke Energy Progress, Llc. to Discuss a Future Relief Request Concerning Containment Metallic Liners and Moisture Barriers Inspection Requirements for the H. B. Robinson Steam Electric Plant, Unit No. 2 Project stage: Meeting ML21053A0472021-02-25025 February 2021 Duke Energy Pre-Submittal Meeting - February 25, 2021 - H. B. Robinson 3rd Interval Containment ISI Relief Request Project stage: Meeting 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 Project stage: Meeting 2021-02-11
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Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) 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 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) 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 ML21259A0992021-11-0404 November 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21214A2222021-08-10010 August 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21209A9962021-08-0202 August 2021 Proposed Alternative Request IST-RR-8 Related to the Inservice Testing Program ML21202A3982021-07-27027 July 2021 Relief Request Proposed Alternatives to American Society of Mechanical Engineers Operation and Maintenance Code Isolation Valve Seal Water System 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 ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20090F8932020-04-29029 April 2020 Relief Request RA-19-0138 Regarding Proposed Alternative to ASME Code, Section XI Volumetric Examination Frequency Requirements RA-19-0428, Relief Request RA-19-0428 for One-Time Pressure Relief Valve Test Frequency Extension2020-02-0404 February 2020 Relief Request RA-19-0428 for One-Time Pressure Relief Valve Test Frequency Extension ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads RNP-RA/13-0018, Relief Request (RR)-8 from Fifth Ten-Year Inservice Inspection Program Plan2013-03-13013 March 2013 Relief Request (RR)-8 from Fifth Ten-Year Inservice Inspection Program Plan ML12314A2882012-12-11011 December 2012 Relief Request-2 for the Fifth 10-Year Interval Inservice Testing Program Plan RNP-RA/12-0113, Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-Year Inservice Inspection...2012-10-25025 October 2012 Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-Year Inservice Inspection... RNP-RA/12-0101, Relief Request (RR)-7 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-year Inservice Inspection Program Plan2012-10-0505 October 2012 Relief Request (RR)-7 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Value (SI-837) for Fifth Ten-year Inservice Inspection Program Plan ML12262A3622012-10-0101 October 2012 Relief Request No. 2 for the Fifth 10-Year Interval Inservice Inspection Program Plan RNP-RA/12-0079, Revised Response to NRC Request for Additional Information Related to Relief Request (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan2012-08-0909 August 2012 Revised Response to NRC Request for Additional Information Related to Relief Request (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan ML12181A1262012-07-13013 July 2012 Relief Request-4 for the Fifth 10-Year Interval Inservice Inspection Program Plan ML12174A0182012-07-13013 July 2012 Relief Request-1 for the Fifth 10-Year Interval Inservice Testing Program ML12174A0102012-07-13013 July 2012 Relief Request -3 for Fifth 10-Year Interval Inservice Testing Program Plan ML12167A2152012-07-13013 July 2012 Relief Request (RR)-6 for the Fifth 10-Year Interval Inservice Inspection Program Plan ML12115A0692012-05-0404 May 2012 Request for Additional Information Related to Relief Requests RR-5 and RR-6 for the Fifth Ten-Year Interval Inservice Inspection Program Plant RNP-RA/08-0129, Request for Extension for Implement Ion of License Amendment Related to Control Room Habitability2009-01-0707 January 2009 Request for Extension for Implement Ion of License Amendment Related to Control Room Habitability ML0827302702008-10-22022 October 2008 Request for Relief from ASME Code, Section XI, Appendix Viii, Supplement 2 and Supplement 10 Weld Examination Requirements ML0427400822004-09-29029 September 2004 Third 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 34 ML0411702632004-04-21021 April 2004 Relief, ASME Code, Section XI, Appendix Viii, Supplement 10, Qualification Requirements for Inspection of Dissimilar Metal Piping Welds, for the Fourth 10-year Inservice Inspection (ISI) Interval, MC1639 RNP-RA/03-0125, Inservice Testing Program, Relief Request IST-RR-8 for Comprehensive Tests2003-10-0707 October 2003 Inservice Testing Program, Relief Request IST-RR-8 for Comprehensive Tests ML0233101712002-11-26026 November 2002 Relief, Examination of Control Rod Drive Mechanism Housing Seal Weld 2023-09-25
[Table view] Category:Meeting Summary
MONTHYEARML23129A0012023-06-26026 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 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 ML0923803922009-08-26026 August 2009 08/11-12/2009-Summary of Meeting Re 2009 Us NRC Initial Exam Development Workshop 2023-06-26
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March 17, 2021 LICENSEE: Duke Energy Progress, LLC FACILITY: H. B. Robinson Steam Electric Plant, Unit 2
SUBJECT:
SUMMARY
OF FEBRUARY 25, 2021, 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 (EPID L-2021-LRM-0017)
On February 25, 2021, a Category one public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Duke Energy Progress, LLC (Duke Energy), the licensee of the H. B. Robinson Steam Electric Plant (Robinson) via teleconference due the COVID-19 Public Health Emergency. The purpose of the meeting was to discuss a future relief request concerning containment liners and moisture barriers during the third In-Service Inspection Interval. The meeting notice and agenda, dated February 11, 2021, are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML21042B903. A list of attendees is provided as Enclosure 1.
The licensee presented information (see ADAMS Accession No. ML21053A047) which summarized the licensees upcoming relief request addressing containment Inservice Inspection over the third inspection interval period of September 9, 2019 to September 8, 2020. The licensee also presented the relief request alternative to be considered in the future submittal, its technical and engineering basis and the proposed timeline for submittal.
During the presubmittal meeting, the NRC staff discussed the following questions and the licensee responded as follows;
- 1. The presentation states that if successive examinations are required in accordance with IWE-2420, Successive Inspections, they may be limited to surfaces whose coatings have not been restored to protect against potential future degradation.
Please describe the requirement of IWE-2420 for the successive examinations, and Duke Energys proposed limited examinations.
Duke Energy responded that IWE-2420(b) states that when examination results detect flaws, areas of degradation, or conditions that require an engineering evaluation, in accordance with IWE-3000, Acceptance Standards or IWE-2500, Examination and Pressure Test Requirements (d), and the component is acceptable for continued service, the areas containing such flaws, areas of degradation or conditions shall be reexamined during the next inspection period, as listed in the schedule per IWE-2411, Inspection Program, and in accordance with Table IWE-2500-1, Examination Requirements (E-C).
Specifically, liner panels at Robinson are recoated after examinations are complete when degraded. Duke Energy is seeking relief from the requirement to perform successive examinations in accordance with IWE-2420(b) on subject areas of the liner where coatings have been restored. Duke Energy will provide additional details of the previous examinations made and discuss the engineering justifications for the intended relief in the upcoming submittal.
- 2. In lieu of the acceptance standards required by IWE-3521, Visual Examination, (a) which states that pressure-retaining component corrosion or erosion that exceeds 10% of the nominal wall thickness, the presentation appears to present that Duke Energy -- for corrosion or erosion that exceeds 120% of the minimum wall thickness required by design -- shall require correction or evaluation to meet the requirements of IWE-3122 Acceptance, prior to continued service. It is not clear in the presentation how the nominal wall thickness is established, and are the wall thicknesses shown in slide 7 of the presentation the nominal wall thickness?
Duke responded that per the Updated Final Safety Analysis Report, Chapter 3, Design Criteria - Structures, Components, Equipment and Systems, Section 3.8, Design of Category 1 Structures, ADAMS (ADAMS Accession No. ML20309A747),
the containment liner is designed to serve as a leakproof membrane and is not relied upon for the structural integrity of the containment except for resisting tangential shears in the dome (note: the dome is accessible). Stress conditions in the liner under all conditions of the design have been analyzed to assure that the principle stresses do not exceed the yield or buckling stresses as provided in design stress criteria calculation for the containment dome. The calculation also documents that construction loads on the liner were also considered. Slide 7 does show the nominal wall thicknesses in the note and, in the upcoming submittal, it will fully describe the design analysis associated with the wall thicknesses discussed as shown in the presentation.
- 3. How was the minimum wall thickness required by design established and where are they documented?
Duke Energy responded that the stress condition factors considered in the original analysis calculation including elastic stability, 90% yield stress at the studs, 90%
yield stress due to pressure, and 90% yield stress due to compression. A uniform plate thickness is evaluated to represent material losses, and the plates function is compared to the above limits as documented in this original analysis calculation.
Duke Energy will describe the plate thickness calculation, the factors considered and the related summary results of plate thickness analysis calculation in the upcoming submittal.
- 4. The presentation states that Over the last two intervals more than 400 insulation panels have been removed at various locations and elevations to facilitate inspections resulting in all liner plate wall thicknesses greater than the minimum thickness required by design. During that period did Duke Energy utilize IWE-3521(a) as the acceptance standard, or was the acceptance standard used during that In-service Inspection period that all liner plate wall thicknesses greater than the minimum thickness required by design?
Duke Energy responded that for the previous interval IWE-3510 Standards for Examination Category E-A, Containment Surfaces, was applicable for acceptance of inspections.
- 5. Duke Energys slide presentation proposes that 120% of the minimum wall thickness required by design is the new engineering platform. Please discuss the basis for this new wall thickness standard.
Duke Energy answered that the containment metallic liner is not a pressure vessel and that a value significantly less than the nominal wall thickness is required to maintain the liner design function of providing a leak-tight barrier. In the upcoming docketed submittal Duke Energy will fully justify the parameters selected and the engineering basis for wall thicknesses related to the relief request.
- 6. Please describe the liner corrosion condition in the area of those 400 previously-removed insulation panels.
Duke Energy answered that, in general, for the panels that were removed, areas of corrosion as well as localized pitting have been found, all of which were recoated after inspection. When pitting was found it occurred over a small area. Additionally, for these panels discussed, a structural integrity test alongside an Integrated Leak Rate Test was performed in November 2020 which documented proper liner function which will be detailed and described in the relief request.
- 7. The presentation states that [ Robinson] Unit 2 containment is a post-tensioned concrete containment vessel with a A36 metallic liner. Significantly less than 90% of the liner thickness is required in order to maintain the liner design function of providing a leak-tight barrier. It is unclear in the presentation what specific level, by percentage, of wall thickness provides a leak tight barrier. Please also discuss the percentage that is adequate and the justification for that value.
Duke Energy responded that the statement in the presentation is intended to convey that 50-64% of the nominal wall thickness is sufficient for full function, as documented and justified within the containment systems calculation analysis which will be described in the relief request.
- 8. Additional NRC staff inquiries addressed:
- a. the method of selection of panels to be inspected in the proposed alternative,
- b. inspection results and relevant operating experience of components during previous component exam periods, and
- c. the necessity for the licensee to ensure appropriate technical information is provided in the upcoming proposed alternative.
Duke Energy will consider and evaluate the questions, and the technical and licensing comments presented by the NRC staff and, as appropriate, include adequate and sufficient material for the NRC staff to complete the technical review of the future relief request.
Members of the public were not in attendance. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-5136, or John.Klos@nrc.gov.
/RA/
John Klos, Project Manager Plant Licensing Branch LPL2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No(s). 50-261
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES FEBRUARY 25, 2021 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 (EPID L-2021-LRM-0017)
ATTENDEE REPRESENTING John Klos NRC John Ma NRC Angelo Stubbs NRC Alissa NeuHausen NRC Mark Pyne Duke Energy Angela Staller Duke Energy Austin Keller Duke Energy Winston Stewart Duke Energy Megan Watkins Duke Energy Art Zaremba Duke Energy Chet Sigmon Duke Energy Enclosure
Meeting Notice: ML21042B903 Meeting Summary: ML21068A417 Handouts: ML21053A047 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL/2-2/PM NAME John Klos Rhonda Butler Undine Shoop John Klos DATE 3/9/2021 3/11/2021 3/16/2021 3/17/2021