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EPID:L-2019-LRM-0014, Final Safety Evaluation for Topical Report ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations (Open) |
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MONTHYEARML18236A3712018-09-24024 September 2018 Final Safety Evaluation for Topical Report ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations Project stage: Request ML19077A3672019-03-14014 March 2019 March 14, 2019 Pre-submittal Meeting TS DNBR Safety Limit Change LAR Meeting Slides Project stage: Meeting ML19113A0652019-05-14014 May 2019 Summary of Meeting with Duke Energy to Discuss Proposed License Amendment Request for Shearon Harris, Unit 1, Technical Specification Changes Associated with Departure from Nucleate Boiling Ratio Safety Limit Project stage: Meeting 2019-03-14
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23341A1522023-12-0707 December 2023 December 11, 2023 Public Meeting - RIPE Exemption Request - Licensee Slides ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22153A3842022-06-0606 June 2022 Duke Energy Presentation Material for June 6, 2022 Public Meeting on GSI-191 Closeout ML22091A1332022-04-0101 April 2022 Bru Har Combined 2021 Assessment Meeting Slides ML20100G6342020-04-0909 April 2020 Revised- Bru 2019 Annual Assessment Meeting 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 ML19077A3672019-03-14014 March 2019 March 14, 2019 Pre-submittal Meeting TS DNBR Safety Limit Change LAR Meeting Slides ML18351A1342018-12-20020 December 2018 December 20, 2018 Pre-submittal Meeting Slides for Escw Risk-Informed LAR ML18333A1822018-11-0808 November 2018 Pre-Submittal Meeting - November 8, 2018 - License Amendment Request for Shearon Harris Nuclear Power Plant Emergency Plan Revision ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17250B2382017-08-30030 August 2017 TMRE Presubmittal NRC ML17044A0892017-03-0202 March 2017 EDG SR Presubmittal Meeting March 2, 2017 ML16267A0292016-09-29029 September 2016 SFP Pre-Submittal Meeting Slides - BWR Storage Rack Inserts, Updated NCS Analysis at Harris Nuclear Plant 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) ML14129A3352014-05-0909 May 2014 Summary of Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear 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. ML13212A3372013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting2013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, 7/31/2013 NRC Public Meeting Presentation on NEI 01-012013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13218B3372013-07-30030 July 2013 Handout for 7/30/13 Conference Call Re. Harris Emergency Response Facility Activation Timeliness and Criteria ML13211A3782013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13204A2562013-07-0909 July 2013 Handout - LOOP Voltage Setpoint Change Presubmittal Conference Call - July 9, 2013 ML13170A3352013-06-13013 June 2013 Presentation - NRC Special Inspection Meeting - Harris Reactor Pressure Vessel ML12277A0272012-10-0202 October 2012 Slides - Summary of Meeting with Duke Energy Carolinas to Discuss Noncenservative Technical Specifications License Amendment Requests ML12242A4322012-08-28028 August 2012 Summary of Category 1 Public Meeting - Regulatory Conference and Predecisional Enforcement Conference 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 ML12107A0012012-04-16016 April 2012 Meeting Summary - Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML11354A3782012-02-0808 February 2012 Meeting Handout - Meeting with Carolina Power and Light Suggested Discussion Items Regarding Realistic Large Break Loss-of-Coolant Accident HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-0282012-01-11011 January 2012 Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028 ML12076A1652012-01-11011 January 2012 Meeting Slides - Harris Realistic LBLOCA Question Response Meeting ML1118011132011-06-29029 June 2011 NRC Staff Response to NFPA 805 Transition FAQ 10-0059, Revision 1 ML1113704082011-05-0909 May 2011 Meeting Slides Regarding Human Performance Improvement ML1107301382011-04-21021 April 2011 February 22, 2011, Summary of Pre-application Meeting with Carolina Power & Light and Representatives Regarding Upcoming BWR Boraflew License Amendment Request W/ Public Meeting Slides ML1111000242011-04-20020 April 2011 Meeting Summary - Shearon Harris - List of Attendees ML1014102712010-05-18018 May 2010 Shearon Harris Nuclear Plant Annual Assessment Meeting Slides ML0922900342009-08-17017 August 2009 08/19/09-Meeting Slides for 11th International Seminar on Fire Safety in Nuclear Power Plants and Installations, Risk-Informed, Performance-Based Fire Protection: a U.S. Regulatory Perspective ML0916605042009-06-24024 June 2009 04/21-22/2009 Summary of Category 2 Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition Shearon, Unit 1 and Oconee to NFPA 805 ML0904906122009-02-18018 February 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, February, 2009 ML0829601532008-11-17017 November 2008 Summary of Meeting with Progress Energy Carolinas, Inc., to Discuss Shearon Harris Unit 1 National Fire Protection Association Standard 805 License Amendment Request ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0820703912008-07-17017 July 2008 Meeting Handouts from 7/17/08 Public Meeting on the Harris and Oconee LARs to Transition to NFPA-805 M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0818407312008-06-20020 June 2008 NFPA-805 Workshop Handouts - Harris NFPA-805 Results and Lessons Learned ML0818407352008-06-20020 June 2008 NFPA-805 Workshop Handouts - Harris Fire PRA Lessons Learned ML0812003342008-04-17017 April 2008 NFPA 805 Transition Pilot Plant FAQ Log - April 2008 ML0820504022008-04-16016 April 2008 April 2008 Observation Visit - Shearon Harris -Pilot Plant Transition to NFPA 805 - Performance Monitoring Program 2023-12-07
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Harris Nuclear Plant Pre-Submittal Meeting
March 2019
License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type 2
Duke Energy Attendees Art Zaremba (Manager, Nuclear Fleet Licensing)
Dennis Earp (Fleet Regulatory Affairs)
Jeff Abbott (Manager, Safety Analysis)
James Reed (Safety Analysis) 3 3
Outline Background Information Technical Content Precedent Proposed Changes Applicable Regulatory Requirements/Criteria 4
Background Information Starting with Cycle 24 (Spring 2021), HNP will start transitioning from Framatome Inc. 17x17 HTP fuel to their GAIA fuel design 8 GAIA LTAs introduced in Cycle 20 core in non-limiting locations Cycle 21 design utilized 8 Cycle 22 design utilized 4 No hydraulic dissimilarities between fuel types that would adversely affect performance of the reactor core in full core (GAIA or HTP) or LTA mixed core configurations 5
Background Information NRC has previously reviewed and approved FramatomesTopical Report ANP-10341P-A,
The ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations
[ADAMS Accession No. ML18236A371]
NRC has previously reviewed and approved the following Duke Energy methodologies for
use by HNP:
DPC-NE-2005-P-A, Revision 5, Thermal Hydraulic Statistical Core Design Methodology,
[ADAMS Accession No. ML16049A630]
DPC-NE-3008-P-A, Revision 0, Thermal-Hydraulic Models for Transient Analysis,
[ADAMS Accession No. ML18060A404 (Package)]
DPC-NE-3009-P-A, Revision 0, FSAR/UFSAR Chapter 15 Transient AnalysisMethodology,
[ADAMS Accession No. ML18060A404 (Package)]
6
Background Information Changes necessary to implement GAIA fuel into Duke Energy methods:
Validation of the ORFEO-GAIA critical heat flux correlation used with the VIPRE-01 thermal hydraulic code Calculation of a safety limit for Duke Energys implementation of the ORFEO-GAIA correlation and inclusion in TS 2.1.1.a Calculation of a statistical core design limit for GAIA fuel using the ORFEO-GAIA correlation Development of a mixed core penalty using VIPRE-01 to apply to analysis results for cores containing both 17x17 HTP and GAIA fuel 7
Technical Content Duke Energy is utilizing the same approach used in the Framatome Topical Report in implementing and validating the ORFEO-GAIA correlation with VIPRE-01 The limits and conditions applicable to the ORFEO-GAIA and ORFEO-NMGRID correlations will apply to Duke Energys use of the correlations with VIPRE-01 Submitting a proposed appendix to DPC-NE-2005-P-A that contains the details of the GAIA VIPRE-01 model and details and results of Duke Energys evaluation of the ORFEO-GAIA correlation with VIPRE-01 Establishes safety limit for GAIA fuel Calculation of statistical design limit for GAIA fuel Addressing the application of expanded VIPRE-01 models with mixed cores 8
Precedent Duke Energy reviewed the LARs and NRC approvals of other licensees (listed below), and the approach Duke Energy intends to take is similar to other licensees.
Arkansas Nuclear One: Application dated May 13, 2009 (ADAMS Accession No.
ML091340153); Supplement dated July 8, 2009 (ADAMS Accession No. ML092050637);NRC Safety Evaluation dated September 18, 2009 (ADAMS Accession No. ML092460118)
Modified DNBR safety limit based on a new fuel design and the associated DNB correlations Callaway Plant, Unit 1: Application dated May 8, 2015 (ADAMS Accession No. ML15132A137);
Supplement dated November 9, 2015 (ADAMS Accession No. ML1533A192); NRC Safety
Evaluation dated February 29, 2016 (ADAMS Accession No. ML16020A516)
Adjusted DNBR safety limit and addition of methodology for determining core operating limits 9
Proposed Changes Technical Specification 2.1.1.a Current 7KHGHSDUWXUHIURPQXFOHDWHERLOLQJUDWLR '1%5 VKDOOEHPDLQWDLQHGIRU
the HTP DNB correlation.
Proposed 7KHGHSDUWXUHIURPQXFOHDWHERLOLQJUDWLR '1%5 VKDOOEHPDLQWDLQHGIRU
WKH+73'1%FRUUHODWLRQIRU+73IXHODQGIRUWKH25)(2-GAIA DNB correlation for GAIA fuel.
Technical Specification 6.9.1.6.2 Addition of ANP-10341P-A, The ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations Adjust page format to remove extraneous space between listed methodologies 10
Applicable Regulatory Requirements/Criteria 10 CFR 50.36, Technical Specifications Defines a safety limit as a limit upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity General Design Criterion (GDC) 10, Reactor Design Requires that specified fuel design limits are not exceeded during steady state operation, normal operational transients, and anticipated operational occurrences Accomplished by having a DNB design basis, which corresponds to a 95% probability at a 95% confidence level (95/95 DNB criterion) that DNB will not occur 11
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