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| {{#Wiki_filter:Fixed Incore Detector Methodology Supplement Presentation to Nuclear Regulatory Commission May 9, 2013 | | {{#Wiki_filter:Fixed Incore Detector Methodology Supplement Presentation to Nuclear Regulatory Commission May 9, 2013 |
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| 2 FPL/NextEra Representatives Paul Gurney
| | FPL/NextEra Representatives |
| -Reactor Engineering Supervisor, Seabrook Station Michael O'Keefe
| | * Paul Gurney |
| -Licensing Manager, Seabrook Station Carl O'Farrill
| | - Reactor Engineering Supervisor, Seabrook Station |
| -Core Design Manager, FPL Juno Beach Glen Seeburger
| | * Michael OKeefe |
| -Advisory Engineer, AREVA Lynchburg
| | - Licensing Manager, Seabrook Station |
| | * Carl OFarrill |
| | - Core Design Manager, FPL Juno Beach |
| | * Glen Seeburger |
| | - Advisory Engineer, AREVA Lynchburg 2 |
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| 3 Fixed Incore Detector Methodology Supplement Overview -Seabrook Fixed Incore Detector System (FIDS)
| | Fixed Incore Detector Methodology Supplement |
| | * Overview |
| | - Seabrook Fixed Incore Detector System (FIDS) |
| Overview of fixed incore detectors | | Overview of fixed incore detectors |
| -License Amendment Basis Initial licensing through current status
| | - License Amendment Basis Initial licensing through current status |
| - License Amendment Overview Topical report to supplement initial licensing Addresses changes to detector processing Implementation
| | - License Amendment Overview Topical report to supplement initial licensing Addresses changes to detector processing Implementation 3 |
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| 4 Seabrook Fixed Incore Detector System Seabrook Station
| | Seabrook Fixed Incore Detector System |
| -4 loop Westinghouse NSSS
| | * Seabrook Station |
| -Rated for 3648 MWt Combination fixed and moveable incore detector system for measuring core power distribution
| | - 4 loop Westinghouse NSSS |
| -Use of a fixed incore detector system is unique for operating Westinghouse designed reactors
| | - Rated for 3648 MWt |
| | * Combination fixed and moveable incore detector system for measuring core power distribution |
| | - Use of a fixed incore detector system is unique for operating Westinghouse designed reactors 4 |
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| 5 Seabrook Fixed Incore Detector System 58 combination fixed and moveable incore detector assemblies Mechanical and electrical connections for each assembly are located at the seal table Each original assembly contains a moveable incore detector path Replacement assemblies do not have a moveable incore detector path
| | Seabrook Fixed Incore Detector System |
| | * 58 combination fixed and moveable incore detector assemblies |
| | * Mechanical and electrical connections for each assembly are located at the seal table |
| | * Each original assembly contains a moveable incore detector path |
| | * Replacement assemblies do not have a moveable incore detector path 5 |
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| |
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| 6 Seabrook Fixed Incore Detector System The fixed incore detectors use a platinum emitter
| | Seabrook Fixed Incore Detector System |
| -For fixed incore detector applications platinum is unique Most fixed detector applications use a rhodium emitter
| | * The fixed incore detectors use a platinum emitter |
| -Platinum is largely gamma sensitive Some sensitivity to neutrons
| | - For fixed incore detector applications platinum is unique Most fixed detector applications use a rhodium emitter |
| -Platinum is a long life emitter
| | - Platinum is largely gamma sensitive Some sensitivity to neutrons |
| | - Platinum is a long life emitter 6 |
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| 7 Seabrook Fixed Incore Detector System
| | Seabrook Fixed Incore Detector System 7 |
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| 8 License Amendment Basis Initial FIDS Licensing Background
| | License Amendment Basis |
| -License Amendment Request (LAR) to utilize FIDS for core power distribution monitoring submitted November 1992
| | * Initial FIDS Licensing Background |
| -Technical basis for methodology documented in topical report YAEC-1855P Seabrook Station Unit 1 Fixed Incore Detector System Analysis -Validation of FIDS methodology was good agreement between fixed and moveable flux maps obtained in cycles 1 & 2
| | - License Amendment Request (LAR) to utilize FIDS for core power distribution monitoring submitted November 1992 |
| | - Technical basis for methodology documented in topical report YAEC-1855P Seabrook Station Unit 1 Fixed Incore Detector System Analysis |
| | - Validation of FIDS methodology was good agreement between fixed and moveable flux maps obtained in cycles 1 & 2 8 |
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| 9 License Amendment Basis NRC Issued License Amendment 27 in December 1993 Conditional acceptance of FIDS for power distribution monitoring
| | License Amendment Basis |
| -Additional flux maps required in cycles 3 & 4
| | * NRC Issued License Amendment 27 in December 1993 |
| -Required a follow
| | * Conditional acceptance of FIDS for power distribution monitoring |
| -up report documenting continued consistency of results Follow-up report YAEC | | - Additional flux maps required in cycles 3 & 4 |
| -1931 submitted in March of 1996 | | - Required a follow-up report documenting continued consistency of results |
| -Demonstrated continued acceptability of the FIDS methodology FIDS used for flux mapping since cycle 5, December 1995
| | * Follow-up report YAEC-1931 submitted in March of 1996 |
| | - Demonstrated continued acceptability of the FIDS methodology |
| | * FIDS used for flux mapping since cycle 5, December 1995 9 |
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| 10 License Amendment Basis Replacement FIDS
| | License Amendment Basis |
| -Project to replace FIDS initiated in 2006
| | * Replacement FIDS |
| -Platinum emitters still providing a good signal
| | - Project to replace FIDS initiated in 2006 |
| -Mechanical and electrical connections at the seal table were degrading 11 License Amendment Basis YAEC-1855P does not specifically address replacement detectors Design of a replacement FID was a like
| | - Platinum emitters still providing a good signal |
| -for-like detector which met the concept of the "standard detector" "Standard detector" defined in YAEC
| | - Mechanical and electrical connections at the seal table were degrading 10 |
| -1855P -Detectors corrected for individual detector differences
| |
| -Detector material and manufacturing differences
| |
| -Original detectors
| |
| - surface area ratio
| |
|
| |
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| 12 License Amendment Basis Additional factors were necessary for replacement detectors to meet the "standard detector"
| | License Amendment Basis |
| -Manufacturing differences
| | * YAEC-1855P does not specifically address replacement detectors |
| -Platinum purity differences
| | * Design of a replacement FID was a like-for-like detector which met the concept of the standard detector |
| -Pt-195 depletion
| | * Standard detector defined in YAEC-1855P |
| | - Detectors corrected for individual detector differences |
| | - Detector material and manufacturing differences |
| | - Original detectors - surface area ratio 11 |
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| 13 License Amendment Basis Gamma Correction Factor
| | License Amendment Basis |
| - GCF -Manufacturing and purity differences
| | * Additional factors were necessary for replacement detectors to meet the standard detector |
| -Determined by direct measurement Platinum Depletion Factor
| | - Manufacturing differences |
| - PDF -Accounts for aging differences between original and replacement detectors 14 License Amendment Basis Detector Replacements Extensive post
| | - Platinum purity differences |
| -modification testing
| | - Pt-195 depletion 12 |
| -Validate performance of replacement FIDS
| |
| -Post modification testing completed before using the replacement detectors for power distribution monitoring
| |
|
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| 15 License Amendment Basis NRC Modification Inspection (Spring 2012)
| | License Amendment Basis |
| -Questioned the 10CFR50.59 Evaluation for the flux mapping software changes implemented for replacement detectors
| | * Gamma Correction Factor - GCF |
| -A previous change (2002) to the flux mapping software was self
| | - Manufacturing and purity differences |
| -identified as part of this review
| | - Determined by direct measurement |
| -Change involved the neutron sensitive component of the detector signal Pt-195 16 License Amendment Basis YAEC 1855P
| | * Platinum Depletion Factor - PDF |
| -Neutron component of signal Assumed to be 25% of total signal
| | - Accounts for aging differences between original and replacement detectors 13 |
| -Weighted by thermal flux
| |
| -Increasing measured
| |
| -to-predicted signal differences observed starting in cycle 6 | |
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| 17 License Amendment Basis Improved prediction of the neutron component of signal Neutron Conversion Factor (NCF)
| | License Amendment Basis |
| -Based on Predicted gamma signal and neutron reaction rate Measured signal
| | * Detector Replacements |
| -Provides better estimate of neutron component of the detector signal -Implemented in Cycle 9 (2002)
| | * Extensive post-modification testing |
| | - Validate performance of replacement FIDS |
| | - Post modification testing completed before using the replacement detectors for power distribution monitoring 14 |
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| 18 License Amendment Basis Changes were considered input changes
| | License Amendment Basis |
| -GCF & PDF (for replacement detectors)
| | * NRC Modification Inspection (Spring 2012) |
| -NCF (for neutron signal component)
| | - Questioned the 10CFR50.59 Evaluation for the flux mapping software changes implemented for replacement detectors |
| -Did not affect the power distribution processing methodology
| | - A previous change (2002) to the flux mapping software was self-identified as part of this review |
| | - Change involved the neutron sensitive component of the detector signal Pt-195 15 |
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| 19 License Amendment Basis Actions Taken Following Inspection
| | License Amendment Basis |
| -Contracted AREVA to prepare a topical report to address the changes made to the flux mapping software Initial system development by YAEC, now part of AREVA Extensive FIDS operational performance data (15 cycles) used for validation Technically robust, complete and comprehensive validation Detailed data analysis results available to facilitate NRC review 20 License Amendment Overview New COLR reference to be added to Technical Specifications
| | * YAEC 1855P |
| -Topical Report Supplement YAEC
| | - Neutron component of signal Assumed to be 25% of total signal |
| -1855P -Replacement Detectors | | - Weighted by thermal flux |
| -Neutron conversion factor
| | - Increasing measured-to-predicted signal differences observed starting in cycle 6 16 |
| -Uncertainty Analysis
| |
|
| |
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| 21 License Amendment Overview Replacement Detectors
| | License Amendment Basis |
| -Describe the methodology used to incorporate replacement detectors into flux mapping software Gamma Correction Factor Platinum Depletion Factor
| | * Improved prediction of the neutron component of signal |
| -"Standard Detector" Relationship to initial licensing basis
| | * Neutron Conversion Factor (NCF) |
| | - Based on Predicted gamma signal and neutron reaction rate Measured signal |
| | - Provides better estimate of neutron component of the detector signal |
| | - Implemented in Cycle 9 (2002) 17 |
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| 22 License Amendment Overview Neutron Conversion Factor
| | License Amendment Basis |
| -Basis for NCF
| | * Changes were considered input changes |
| -Relationship to initial licensing input assumption 25% of detector signal
| | - GCF & PDF (for replacement detectors) |
| | - NCF (for neutron signal component) |
| | - Did not affect the power distribution processing methodology 18 |
|
| |
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| 23 License Amendment Overview Uncertainty Analysis
| | License Amendment Basis |
| -2 components of the current licensed uncertainty analysis potentially affected Reproducibility for replacement detectors Detector processing uncertainty
| | * Actions Taken Following Inspection |
| -Total and integral detector processing
| | - Contracted AREVA to prepare a topical report to address the changes made to the flux mapping software Initial system development by YAEC, now part of AREVA Extensive FIDS operational performance data (15 cycles) used for validation Technically robust, complete and comprehensive validation Detailed data analysis results available to facilitate NRC review 19 |
| -Failed detector analysis to support minimum requirements
| |
|
| |
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| 24 License Amendment Overview Draft Schedule
| | License Amendment Overview |
| -Submit amendment
| | * New COLR reference to be added to Technical Specifications |
| - July 2013 -Request approval | | - Topical Report |
| - May 1, 2014 Supplemental topical report to be added as a COLR reference in Technical Specification section 6.8}} | | * Supplement YAEC-1855P |
| | - Replacement Detectors |
| | - Neutron conversion factor |
| | - Uncertainty Analysis 20 |
| | |
| | License Amendment Overview |
| | * Replacement Detectors |
| | - Describe the methodology used to incorporate replacement detectors into flux mapping software Gamma Correction Factor Platinum Depletion Factor |
| | - Standard Detector Relationship to initial licensing basis 21 |
| | |
| | License Amendment Overview |
| | * Neutron Conversion Factor |
| | - Basis for NCF |
| | - Relationship to initial licensing input assumption 25% of detector signal 22 |
| | |
| | License Amendment Overview |
| | * Uncertainty Analysis |
| | - 2 components of the current licensed uncertainty analysis potentially affected Reproducibility for replacement detectors Detector processing uncertainty |
| | - Total and integral detector processing |
| | - Failed detector analysis to support minimum requirements 23 |
| | |
| | License Amendment Overview |
| | * Draft Schedule |
| | - Submit amendment - July 2013 |
| | - Request approval - May 1, 2014 |
| | * Supplemental topical report to be added as a COLR reference in Technical Specification section 6.8 24}} |
Letter Sequence Meeting |
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MONTHYEARML0705206062007-03-19019 March 2007 Issuance of Amendments Power Range Neutron Flux High Negative Rate Trip and Editorial Changes (Tac Nos. MD1490 and MD1491) Project stage: Approval ML0708104202007-03-19019 March 2007 Technical Specification for Amendment 261 Power Range Neutron Flux High Negative Rate Trip Project stage: Acceptance Review ML13099A2152013-04-18018 April 2013 Forthcoming Meeting with Nextera Energy Seabrook, LLC (Nextera) Regarding a Pre-Submittal for a Fixed Incore Detector License Amendment Request Project stage: Meeting ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request Project stage: Meeting ML13133A2412013-06-12012 June 2013 5/9/2013 - Summary of Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request Project stage: Meeting 2013-04-18
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19050A4602019-02-13013 February 2019 Handouts from the Public at the February 13, 2019, Seabrook ASR Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML17129A3942017-05-0909 May 2017 Status of Safety Review of Seabrook License Renewal for May 9, 2017, Public Meeting on ASR in Seabrook LRA ML17129A3842017-05-0909 May 2017 NextEra Presentation at May 9, 2017, Public Meeting Re ASR in License Renewal ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML15176A5012015-06-18018 June 2015 Aam Attendance List for June 18, 2015 ML13357A0462013-12-23023 December 2013 Update on ASR ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML14023A7212013-12-18018 December 2013 No More Fukushima Statement for NRC Public Meeting on Dec 18, 2013 ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0608202482006-03-23023 March 2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance ML0603805612006-02-0606 February 2006 Meeting with FLP, Meeting Handouts, Proposed Submittal to Adopt Quality Assurance Topical Report ML0727105482005-12-16016 December 2005 Measurement Uncertainty Recapture Fple/Caldon - NRC Meeting ML0512201092005-04-22022 April 2005 Slides & Handouts from Meeting with FPL Energy Seabrook, LLC, Regarding Implementation of Technical Specification 3/4.8.1.1 ML0507302062005-03-14014 March 2005 NRC Slides for Public Meeting of Seabrook Station Annual Assessment ML0414201102004-05-20020 May 2004 Public Meeting Handouts Re Power Uprate License Amendment Request for Seabrook Station Unit No. 1 ML0406304312004-03-0303 March 2004 Powerpoint Presentation Slides for Meeting with Florida Power & Light Company Regarding Planned Power Uprate Request for Seabrook Station, Unit No. 1 ML0317404312003-06-12012 June 2003 Sign in Sheet ML0232601592002-11-14014 November 2002 Meeting Handout, Seabrook Steam Generator Tube Assessment Project 2023-06-26
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22130A1282022-05-10010 May 2022 Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML21168A1452021-06-22022 June 2021 Annual Assessment Meeting Slides ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19042A1102019-02-13013 February 2019 Presentation Slides - 2019 Seabrook Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16168A4122016-06-15015 June 2016 Slides for Public Meeting with NextEra Energy Regarding Seabrook Station ASR License Amendment ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML14190B0432014-07-0909 July 2014 Annual Assessment Meeting Performance Slides - June 24 2014 ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML13357A0462013-12-23023 December 2013 Update on ASR ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12236A3852012-08-23023 August 2012 Memo Summary of NextEra Energy Seabrook Drop in Visit and Slides, August 22, 2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1211604142012-04-23023 April 2012 Structural Assessment of Seabrook Station - Role of Concrete Material Testing ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I SBK-L-11190, Supplement to Request for Closed Meeting to Discuss Proprietary Test2011-09-19019 September 2011 Supplement to Request for Closed Meeting to Discuss Proprietary Test ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML12054A6412011-05-24024 May 2011 Concrete Degradation - Alkali Silica Reaction, W/Handwritten Notes ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1019703702010-07-19019 July 2010 License Renewal Process Overview ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML1011004582010-04-20020 April 2010 NRC Slides for Seabrook Annual Assessment Meeting, April 14, 2010 ML0927403042009-09-22022 September 2009 NextEra Letter and Slide Presentation to NRC Seabrook Regulatory Conference, Dated 9/22/09 ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0710002082007-03-29029 March 2007 Aam Slides for EOC 2006-07 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0727105992006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power ML0727106062006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power ML0608202482006-03-23023 March 2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance ML0601300312005-12-16016 December 2005 Meeting Slides, Measurement Uncertainty Recapture Fple/Caldon - NRC Meeting December 16, 2005 2023-06-26
[Table view] |
Text
Fixed Incore Detector Methodology Supplement Presentation to Nuclear Regulatory Commission May 9, 2013
FPL/NextEra Representatives
- Reactor Engineering Supervisor, Seabrook Station
- Licensing Manager, Seabrook Station
- Core Design Manager, FPL Juno Beach
- Advisory Engineer, AREVA Lynchburg 2
Fixed Incore Detector Methodology Supplement
- Seabrook Fixed Incore Detector System (FIDS)
Overview of fixed incore detectors
- License Amendment Basis Initial licensing through current status
- License Amendment Overview Topical report to supplement initial licensing Addresses changes to detector processing Implementation 3
Seabrook Fixed Incore Detector System
- 4 loop Westinghouse NSSS
- Rated for 3648 MWt
- Combination fixed and moveable incore detector system for measuring core power distribution
- Use of a fixed incore detector system is unique for operating Westinghouse designed reactors 4
Seabrook Fixed Incore Detector System
- 58 combination fixed and moveable incore detector assemblies
- Mechanical and electrical connections for each assembly are located at the seal table
- Each original assembly contains a moveable incore detector path
- Replacement assemblies do not have a moveable incore detector path 5
Seabrook Fixed Incore Detector System
- The fixed incore detectors use a platinum emitter
- For fixed incore detector applications platinum is unique Most fixed detector applications use a rhodium emitter
- Platinum is largely gamma sensitive Some sensitivity to neutrons
- Platinum is a long life emitter 6
Seabrook Fixed Incore Detector System 7
License Amendment Basis
- Initial FIDS Licensing Background
- License Amendment Request (LAR) to utilize FIDS for core power distribution monitoring submitted November 1992
- Technical basis for methodology documented in topical report YAEC-1855P Seabrook Station Unit 1 Fixed Incore Detector System Analysis
- Validation of FIDS methodology was good agreement between fixed and moveable flux maps obtained in cycles 1 & 2 8
License Amendment Basis
- NRC Issued License Amendment 27 in December 1993
- Conditional acceptance of FIDS for power distribution monitoring
- Additional flux maps required in cycles 3 & 4
- Required a follow-up report documenting continued consistency of results
- Follow-up report YAEC-1931 submitted in March of 1996
- Demonstrated continued acceptability of the FIDS methodology
- FIDS used for flux mapping since cycle 5, December 1995 9
License Amendment Basis
- Project to replace FIDS initiated in 2006
- Platinum emitters still providing a good signal
- Mechanical and electrical connections at the seal table were degrading 10
License Amendment Basis
- YAEC-1855P does not specifically address replacement detectors
- Design of a replacement FID was a like-for-like detector which met the concept of the standard detector
- Standard detector defined in YAEC-1855P
- Detectors corrected for individual detector differences
- Detector material and manufacturing differences
- Original detectors - surface area ratio 11
License Amendment Basis
- Additional factors were necessary for replacement detectors to meet the standard detector
- Manufacturing differences
- Platinum purity differences
- Pt-195 depletion 12
License Amendment Basis
- Gamma Correction Factor - GCF
- Manufacturing and purity differences
- Determined by direct measurement
- Platinum Depletion Factor - PDF
- Accounts for aging differences between original and replacement detectors 13
License Amendment Basis
- Extensive post-modification testing
- Validate performance of replacement FIDS
- Post modification testing completed before using the replacement detectors for power distribution monitoring 14
License Amendment Basis
- NRC Modification Inspection (Spring 2012)
- Questioned the 10CFR50.59 Evaluation for the flux mapping software changes implemented for replacement detectors
- A previous change (2002) to the flux mapping software was self-identified as part of this review
- Change involved the neutron sensitive component of the detector signal Pt-195 15
License Amendment Basis
- Neutron component of signal Assumed to be 25% of total signal
- Weighted by thermal flux
- Increasing measured-to-predicted signal differences observed starting in cycle 6 16
License Amendment Basis
- Improved prediction of the neutron component of signal
- Neutron Conversion Factor (NCF)
- Based on Predicted gamma signal and neutron reaction rate Measured signal
- Provides better estimate of neutron component of the detector signal
- Implemented in Cycle 9 (2002) 17
License Amendment Basis
- Changes were considered input changes
- GCF & PDF (for replacement detectors)
- NCF (for neutron signal component)
- Did not affect the power distribution processing methodology 18
License Amendment Basis
- Actions Taken Following Inspection
- Contracted AREVA to prepare a topical report to address the changes made to the flux mapping software Initial system development by YAEC, now part of AREVA Extensive FIDS operational performance data (15 cycles) used for validation Technically robust, complete and comprehensive validation Detailed data analysis results available to facilitate NRC review 19
License Amendment Overview
- New COLR reference to be added to Technical Specifications
- Topical Report
- Replacement Detectors
- Neutron conversion factor
- Uncertainty Analysis 20
License Amendment Overview
- Describe the methodology used to incorporate replacement detectors into flux mapping software Gamma Correction Factor Platinum Depletion Factor
- Standard Detector Relationship to initial licensing basis 21
License Amendment Overview
- Neutron Conversion Factor
- Basis for NCF
- Relationship to initial licensing input assumption 25% of detector signal 22
License Amendment Overview
- 2 components of the current licensed uncertainty analysis potentially affected Reproducibility for replacement detectors Detector processing uncertainty
- Total and integral detector processing
- Failed detector analysis to support minimum requirements 23
License Amendment Overview
- Submit amendment - July 2013
- Request approval - May 1, 2014