Letter Sequence Meeting |
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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
[Table view] |
Text
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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