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| {{#Wiki_filter:}} | | {{#Wiki_filter:Duke Energy / NRC Pre-submittal Meeting License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (MTC) Measurement Methodology Presenter: |
| | David Bortz Catawba and McGuire Nuclear Stations August 30, 2021 Duke Energy - Safety Analysis Models Duke / NRC Meeting |
| | |
| | Participants |
| | * Dave Bortz (Safety Analysis Models) |
| | * Mike Blom (Director Fuel Management and Design) |
| | * Jeff Abbott (Manager Safety Analysis Models) |
| | * Art Zaremba (Fleet Licensing Manager) |
| | Duke Energy - Safety Analysis Models Duke / NRC Meeting 2 |
| | |
| | Outline |
| | * Overview of DPC-NE-1007-P |
| | * EOC MTC Measurement |
| | * Summary of Changes |
| | * Motivation for Changes |
| | * Methodology Revisions |
| | * Schedule Duke Energy - Safety Analysis Models Duke / NRC Meeting 3 |
| | |
| | Overview of DPC-NE-1007-P |
| | * Describes the methodology to conditionally exempt the performance of the EOC MTC measurement at CNS and MNS |
| | * Technical Specification SR 3.1.3.2 requires verification of the MTC within 7 effective full power days of reaching the equivalent of an equilibrium core boron concentration of 300 ppm at RTP conditions |
| | * Conditional Exemption based on: |
| | - Core performance criteria being satisfied to demonstrate the reactor core is operating as designed |
| | - Calculation of the EOC 300 ppm RTP MTC accounting for uncertainty and differences between predicted and actual core performance |
| | - Verification the calculated MTC is within the SR 3.1.3.2 limit |
| | * If any single core performance criterion is not met, an EOC MTC measurement is required Duke Energy - Safety Analysis Models Duke / NRC Meeting 4 |
| | |
| | EOC MTC Measurement |
| | * Required by SR 3.1.3.2 |
| | * Measurement is an infrequent plant evolution |
| | * Plant systems operated in a mode or condition not typical of steady state operation |
| | * Introduces a reactivity transient |
| | * Difficult to accurately perform |
| | * Loss in plant availability (decrease in thermal efficiency during the test) |
| | * Potential for a reactivity event due to a human performance error or unanticipated equipment issue Duke Energy - Safety Analysis Models Duke / NRC Meeting 5 |
| | |
| | Summary of Changes |
| | * Remove the incore tilt performance criterion |
| | * Modify the power distribution performance criterion to prevent a false positive failure |
| | * Add an alternative method for determining the most-negative MTC safety analysis limit |
| | * No Technical Specification changes required Duke Energy - Safety Analysis Models Duke / NRC Meeting 6 |
| | |
| | Motivation for Methodology Changes |
| | * Prevent the unnecessary performance of an infrequent plant evolution, reactivity transient and loss of plant efficiency |
| | * Eliminate a condition where an indeterminate instrument issue causes the power distribution performance criteria to be exceeded |
| | * Increase margin to the safety analysis most-negative MTC limit to accommodate the introduction of advanced fuel designs and fuel management strategies Duke Energy - Safety Analysis Models Duke / NRC Meeting 7 |
| | |
| | Incore Tilt Methodology Revision |
| | * Remove the incore tilt criterion based on experience with using the method |
| | - Frequently challenged |
| | - Responsible for all exemption failures |
| | - Negligibly impacts the magnitude of the MTC |
| | - Power distribution reaction rate criterion available to demonstrate core is operating as designed |
| | * Incore tilts are not uncommon. Can results from: |
| | - differences in loop flows and inlet temperatures |
| | - Asbuilt fuel and burnable absorber fabrication |
| | - Intentional Duke Energy - Safety Analysis Models Duke / NRC Meeting 8 |
| | |
| | Power Distribution Methodology Revision |
| | * Modify the performance criteria to remove the single failure criterion |
| | * Current criteria is +/- 10% assembly average reaction rate error and remains unchanged |
| | * Any single location with a reaction rate error greater than 10% absolute results in a failure of the criterion |
| | * New criterion requires multiple failures |
| | * Eliminates the condition where a measurement due to an indeterminate instrument issue causes a false positive (criteria exceeded) |
| | Duke Energy - Safety Analysis Models Duke / NRC Meeting 9 |
| | |
| | SA MTC Limit Methodology Revision |
| | * Add an alternate approach for calculating the EOC most negative MTC Safety Analysis limit |
| | * Removes unnecessary conservatism in the method |
| | * Current method is deterministic |
| | * New method statistically combines parameters used to calculate the limit |
| | * Methodology revision increases analysis margin to support higher burnup fuel designs and potential two-year fuel management strategies Duke Energy - Safety Analysis Models Duke / NRC Meeting 10 |
| | |
| | Schedule |
| | * Expected submittal - September 2021 |
| | * One year review and approval from NRC acceptance Duke Energy - Safety Analysis Models Duke / NRC Meeting 11}} |
Letter Sequence Request |
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EPID:L-2021-LRM-0078, License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (Mtc) Measurement Methodology (Open) |
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Category:Meeting Briefing Package/Handouts
MONTHYEARRA-24-0203, Regulatory Conference Supporting Information2024-07-31031 July 2024 Regulatory Conference Supporting Information ML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML22336A0382022-12-0808 December 2022 Presentation Slides December 8, 2022, pre-submittal Meeting to Discuss Proposed License Amendment Request Regarding TS 3.7.11, Control Room Area Chilled Water System (Cracws) ML22325A3142022-11-30030 November 2022 November 30, 2022, Pre-Submittal Presentation Slides TSTF-505 and 10 CFR 50.69 (L-2022-LRM-0084) ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22067A1992022-03-0303 March 2022 Annual Assessment Meeting Presentation ML21336A1422021-12-0707 December 2021 December 7, 2021, Pre-submittal Presentation Slides Regarding Embedded Flaw Repair Relief Request - Revised ML21327A2112021-11-23023 November 2021 December 7, 2021, Pre-submittal Presentation Regarding Embedded Flaw Repair Relief Request ML21236A2862021-08-30030 August 2021 License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (Mtc) Measurement Methodology ML21116A2542021-04-15015 April 2021 C2R24 Relief Request Pre-Submittal Slides Call 1 ML21089A1732021-03-30030 March 2021 EOC Slides Final ML21081A1242021-03-22022 March 2021 EOC Slides Final 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 ML18239A3682018-08-27027 August 2018 License Amendment Request Pre-Submittal Conference Call August 29, 2018 ML18157A0322018-06-0606 June 2018 Nw System LAR Presubmittal Meeting ML18089A0532018-03-30030 March 2018 Summary of Public Meeting with McGuire Nuclear Station ML17278A1342017-10-0404 October 2017 Duke Presentation for Public Meeting 09-20-17 ML16242A2382016-08-30030 August 2016 Catawba/Mcguiproposed Changes to Technical Specification 3.8.1, AC Sources - Operating. ML16112A0112016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems ML16117A4632016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems (Revised) ML16082A0682016-03-21021 March 2016 Summary of Meeting with the Public Concerning the Annual Assessment of McGuire Nuclear Station, Units 1 and 2 ML16081A3352016-03-17017 March 2016 Summary of Meeting with Public Concerning Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15106A0302015-04-15015 April 2015 Meeting Summary with Public to Discuss the Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15106A0222015-04-15015 April 2015 Summary of Meeting with Public to Discuss Annual Assessment of McGuire Nuclear Station, Units 1 and 2, in Huntersville, North Carolina ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson ML15085A4242015-03-24024 March 2015 Nuclear Reactor Effluents Webinar ML14136A1302014-05-15015 May 2014 End of Cycle Meeting Summary Memo ML14126A6792014-05-0606 May 2014 Summary of Public Meeting with Catawba, Units 1 & 2 to Discuss Annual Assessment ML14016A1692014-01-0707 January 2014 Presentation Regarding Use of High Density Polyethylene (Hdpe) Piping as Replacement for Underground Piping January 7, 2014 -Catawba Nuclear Station Hdpe Relief Request 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. ML13218B2272013-08-0606 August 2013 Vital Battery Replacement, 08-05-13 ML13210A3002013-07-30030 July 2013 Proposed Relief Request 13-MN-002 Risk-Informed/Safety Based (Ris_B) ISI Alternative for Class 1 and 2 Piping ML13127A0802013-04-18018 April 2013 Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP ML12261A2232012-09-17017 September 2012 September 11, 2012 - Summary of Category 1 Public Meeting Held in Atlanta, Ga 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 ML12128A0522012-05-0303 May 2012 Annual Assessment Meeting, Slides ML12117A2542012-04-26026 April 2012 2011 EOC Slides ML11125A0122011-05-0404 May 2011 Summary of Public Meeting with Duke Energy Carolinas, LLC, McGuire, to Discuss Nrc'S Reactor Oversight Process and Nrc'S Annual Assessment of Plant Safety Performance for the Period of 01/01/10 - 12/31/10 ML11097A0272011-04-14014 April 2011 Summary of Meeting with Duke Energy Carolinas, LLC, on Upcoming Submittal of License Amendments Regarding Implementation of National Fire Protection Association Standard 805, (TACs ME5767 & ME5768, Catawba 1 & 2 ME5769 & ME5770 Mcguire 1 & ML0927304602009-10-0707 October 2009 09/01/2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02. Meeting Handouts ML0912803032009-05-0808 May 2009 Summary of Public Meeting/Open House to Provide Opportunities to Discuss Annual Assessment of Catawba Nuclear Station with Public ML0833000612008-11-24024 November 2008 Meeting Slides for Category 1 Public Meeting with Duke Energy Carolinas, Regarding a Request for Additional Information on Duke'S Response to GL 200-04 ML0826708642008-09-18018 September 2008 Regulatory Conference - Service Water Strainer Backwash System ML0822001632008-08-0101 August 2008 Meeting Slides, Performance Discussion Meeting to Provide the NRC Staff with an Update of Plant Performance at the Catawba Nuclear Station ML0819903672008-07-15015 July 2008 Handouts from Duke Energy & NRC Meeting - NQA-1 Based QA Program Conversion ML0720502202007-05-0303 May 2007 Public Meeting Slides for Catawba ML0719903572007-04-30030 April 2007 EOC Meeting Slides 2024-07-31
[Table view] Category:Slides and Viewgraphs
MONTHYEARRA-24-0203, Regulatory Conference Supporting Information2024-07-31031 July 2024 Regulatory Conference Supporting Information ML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML23087A2972023-04-17017 April 2023 Annual Assessment Meeting Presentation ML22336A0382022-12-0808 December 2022 Presentation Slides December 8, 2022, pre-submittal Meeting to Discuss Proposed License Amendment Request Regarding TS 3.7.11, Control Room Area Chilled Water System (Cracws) ML22325A3142022-11-30030 November 2022 November 30, 2022, Pre-Submittal Presentation Slides TSTF-505 and 10 CFR 50.69 (L-2022-LRM-0084) ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22109A2122022-04-20020 April 2022 Duke Energy Pre-Submittal Public April 20, 2022, Meeting Presentation ML22067A1992022-03-0303 March 2022 Annual Assessment Meeting Presentation ML21336A1422021-12-0707 December 2021 December 7, 2021, Pre-submittal Presentation Slides Regarding Embedded Flaw Repair Relief Request - Revised ML21322A3262021-11-29029 November 2021 Duke Energy November 29, 2021 Pre-Submittal Public Meeting Slides for EOF Relocation Licensing Amendment Request ML21327A2112021-11-23023 November 2021 December 7, 2021, Pre-submittal Presentation Regarding Embedded Flaw Repair Relief Request ML21236A2862021-08-30030 August 2021 License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (Mtc) Measurement Methodology ML21116A0662021-04-22022 April 2021 C2R24 Relief Request Pre-Submittal Slides Call 2 ML21116A2542021-04-15015 April 2021 C2R24 Relief Request Pre-Submittal Slides Call 1 ML21089A1732021-03-30030 March 2021 EOC Slides Final ML21081A1242021-03-22022 March 2021 EOC Slides Final ML20134J0052020-05-13013 May 2020 EOC Slides (2) ML20125A2312020-05-0404 May 2020 EOC 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 ML18089A0532018-03-30030 March 2018 Summary of Public Meeting with McGuire Nuclear Station ML17278A1342017-10-0404 October 2017 Duke Presentation for Public Meeting 09-20-17 ML16210A0372016-07-28028 July 2016 16-MN-003 1RN884 Pipe Layout Drawing MC-1418-14.41-02 Info Only ML16117A4632016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems (Revised) ML16112A0112016-04-28028 April 2016 Duke Presentation in Support of April 28, 2016 Pre-Submittal Meeting Catawba Nuclear Station, Units 1 and 2, License Amendment Request Proposed TS Bases Descriptions for Shared Systems ML16082A0682016-03-21021 March 2016 Summary of Meeting with the Public Concerning the Annual Assessment of McGuire Nuclear Station, Units 1 and 2 ML16081A3352016-03-17017 March 2016 Summary of Meeting with Public Concerning Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15230A5942015-08-10010 August 2015 MNS Ice Condenser Door LAR Presentation - 08/12/15 ML15106A0222015-04-15015 April 2015 Summary of Meeting with Public to Discuss Annual Assessment of McGuire Nuclear Station, Units 1 and 2, in Huntersville, North Carolina ML15106A0302015-04-15015 April 2015 Meeting Summary with Public to Discuss the Annual Assessment of Catawba Nuclear Station, Units 1 and 2 ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson ML15085A4242015-03-24024 March 2015 Nuclear Reactor Effluents Webinar ML14136A1302014-05-15015 May 2014 End of Cycle Meeting Summary Memo ML14126A6792014-05-0606 May 2014 Summary of Public Meeting with Catawba, Units 1 & 2 to Discuss Annual Assessment ML14016A1692014-01-0707 January 2014 Presentation Regarding Use of High Density Polyethylene (Hdpe) Piping as Replacement for Underground Piping January 7, 2014 -Catawba Nuclear Station Hdpe Relief Request 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. ML13218B2272013-08-0606 August 2013 Vital Battery Replacement, 08-05-13 ML13210A3002013-07-30030 July 2013 Proposed Relief Request 13-MN-002 Risk-Informed/Safety Based (Ris_B) ISI Alternative for Class 1 and 2 Piping ML13127A0802013-04-18018 April 2013 Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP ML12261A2232012-09-17017 September 2012 September 11, 2012 - Summary of Category 1 Public Meeting Held in Atlanta, Ga ML12128A0522012-05-0303 May 2012 Annual Assessment Meeting, Slides ML12117A2542012-04-26026 April 2012 2011 EOC Slides ML11125A0122011-05-0404 May 2011 Summary of Public Meeting with Duke Energy Carolinas, LLC, McGuire, to Discuss Nrc'S Reactor Oversight Process and Nrc'S Annual Assessment of Plant Safety Performance for the Period of 01/01/10 - 12/31/10 ML1112308322011-05-0303 May 2011 End of Cycle Public Meeting Summary ML11097A0272011-04-14014 April 2011 Summary of Meeting with Duke Energy Carolinas, LLC, on Upcoming Submittal of License Amendments Regarding Implementation of National Fire Protection Association Standard 805, (TACs ME5767 & ME5768, Catawba 1 & 2 ME5769 & ME5770 Mcguire 1 & ML1034807072010-12-14014 December 2010 Public Meeting Summary - Duke Quality Assurance Program Discussion Meeting ML1011604522010-04-26026 April 2010 Summary of Public Meeting with Catawba Nuclear Station to Discuss Nrc'S Reactor Oversight Process and the Nrc'S Annual Assessment of Plant Safety Performance for the Period of January 1, 2009 - December 31, 2009 ML0912803032009-05-0808 May 2009 Summary of Public Meeting/Open House to Provide Opportunities to Discuss Annual Assessment of Catawba Nuclear Station with Public ML0833000612008-11-24024 November 2008 Meeting Slides for Category 1 Public Meeting with Duke Energy Carolinas, Regarding a Request for Additional Information on Duke'S Response to GL 200-04 2024-07-31
[Table view] |
Text
Duke Energy / NRC Pre-submittal Meeting License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (MTC) Measurement Methodology Presenter:
David Bortz Catawba and McGuire Nuclear Stations August 30, 2021 Duke Energy - Safety Analysis Models Duke / NRC Meeting
Participants
- Dave Bortz (Safety Analysis Models)
- Mike Blom (Director Fuel Management and Design)
- Jeff Abbott (Manager Safety Analysis Models)
- Art Zaremba (Fleet Licensing Manager)
Duke Energy - Safety Analysis Models Duke / NRC Meeting 2
Outline
- Overview of DPC-NE-1007-P
- Schedule Duke Energy - Safety Analysis Models Duke / NRC Meeting 3
Overview of DPC-NE-1007-P
- Describes the methodology to conditionally exempt the performance of the EOC MTC measurement at CNS and MNS
- Technical Specification SR 3.1.3.2 requires verification of the MTC within 7 effective full power days of reaching the equivalent of an equilibrium core boron concentration of 300 ppm at RTP conditions
- Conditional Exemption based on:
- Core performance criteria being satisfied to demonstrate the reactor core is operating as designed
- Calculation of the EOC 300 ppm RTP MTC accounting for uncertainty and differences between predicted and actual core performance
- Verification the calculated MTC is within the SR 3.1.3.2 limit
- If any single core performance criterion is not met, an EOC MTC measurement is required Duke Energy - Safety Analysis Models Duke / NRC Meeting 4
EOC MTC Measurement
- Measurement is an infrequent plant evolution
- Plant systems operated in a mode or condition not typical of steady state operation
- Difficult to accurately perform
- Loss in plant availability (decrease in thermal efficiency during the test)
- Potential for a reactivity event due to a human performance error or unanticipated equipment issue Duke Energy - Safety Analysis Models Duke / NRC Meeting 5
Summary of Changes
- Remove the incore tilt performance criterion
- Modify the power distribution performance criterion to prevent a false positive failure
- Add an alternative method for determining the most-negative MTC safety analysis limit
- No Technical Specification changes required Duke Energy - Safety Analysis Models Duke / NRC Meeting 6
Motivation for Methodology Changes
- Prevent the unnecessary performance of an infrequent plant evolution, reactivity transient and loss of plant efficiency
- Eliminate a condition where an indeterminate instrument issue causes the power distribution performance criteria to be exceeded
- Increase margin to the safety analysis most-negative MTC limit to accommodate the introduction of advanced fuel designs and fuel management strategies Duke Energy - Safety Analysis Models Duke / NRC Meeting 7
Incore Tilt Methodology Revision
- Remove the incore tilt criterion based on experience with using the method
- Frequently challenged
- Responsible for all exemption failures
- Negligibly impacts the magnitude of the MTC
- Power distribution reaction rate criterion available to demonstrate core is operating as designed
- Incore tilts are not uncommon. Can results from:
- differences in loop flows and inlet temperatures
- Asbuilt fuel and burnable absorber fabrication
- Intentional Duke Energy - Safety Analysis Models Duke / NRC Meeting 8
Power Distribution Methodology Revision
- Modify the performance criteria to remove the single failure criterion
- Current criteria is +/- 10% assembly average reaction rate error and remains unchanged
- Any single location with a reaction rate error greater than 10% absolute results in a failure of the criterion
- New criterion requires multiple failures
- Eliminates the condition where a measurement due to an indeterminate instrument issue causes a false positive (criteria exceeded)
Duke Energy - Safety Analysis Models Duke / NRC Meeting 9
SA MTC Limit Methodology Revision
- Add an alternate approach for calculating the EOC most negative MTC Safety Analysis limit
- Removes unnecessary conservatism in the method
- Current method is deterministic
- New method statistically combines parameters used to calculate the limit
- Methodology revision increases analysis margin to support higher burnup fuel designs and potential two-year fuel management strategies Duke Energy - Safety Analysis Models Duke / NRC Meeting 10
Schedule
- Expected submittal - September 2021
- One year review and approval from NRC acceptance Duke Energy - Safety Analysis Models Duke / NRC Meeting 11