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Category:Meeting Summary
MONTHYEARML23187A4432023-07-11011 July 2023 6/27/2023, Annual Assessment Meeting for Seabrook Station - Meeting Summary ML23086B9962023-04-0404 April 2023 Summary of March 7, 2023, Meeting with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Revise Emergency Action Level Due to Modification to Containment Fire Detection Equipment ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report ML22144A0022022-09-14014 September 2022 Summary of February 16, and May 18, 2022, Meetings with Nextera Energy/Florida Power & Light Company Regarding Planned Submittal of License Amendment Request for a Common Fleet Emergency Plan ML22146A3422022-06-13013 June 2022 February 23, Summary of Meetings with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML22153A1672022-06-0202 June 2022 Annual Assessment Meeting for Seabrook Station - Meeting Summary ML21336A4072021-12-0707 December 2021 Summary of Conference Call Regarding the Fall 2021 Steam Generator Tube Inspections ML21168A1522021-06-22022 June 2021 Annual Assessment Meeting Summary ML20174A2682020-06-22022 June 2020 June 3, 2020, Seabrook Annual Assessment Summary ML19073A0172019-03-21021 March 2019 Summary of Meeting with Nextera Energy Seabrook, LLC, on Proposed Relief Requests for the Containment Spray System for the Seabrook Station, Unit No. 1 ML19046A3832019-02-26026 February 2019 Meeting Summary of February 13, 2019, Public Meeting in Hampton, New Hampshire Alkali-Silica Reaction License Amendment Request and License Renewal Application ML18136A9052018-05-31031 May 2018 Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 ML18135A2462018-05-31031 May 2018 Summary of April 24, 2018, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of License Amendment Request to Adopt Standard Technical Specification 3.0.6 ML18142A2932018-05-21021 May 2018 2018 Annual Assessment Meeting Summary ML17340A1862017-12-14014 December 2017 Summary of November 17, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction - Requests for Additional Information (CAC No. MF8260; EPID L-2016-LLA-0007) ML17310B2062017-11-20020 November 2017 Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 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) ML17216A1732017-09-0707 September 2017 Notice of Meeting with Florida Power & Light Company and NextEra Energy to Discuss Closing Out Generic Safety Issue-191 and Generic Letter 2004-02 ML17172A1322017-06-20020 June 2017 Summary of Annual Assessment Meeting for Seabrook Station, Unit 1, Held on 6/7/2017 ML17137A0292017-06-0505 June 2017 Summary of Meeting Held on May 9, 2017, Between the USNRC Staff and NextEra Representatives to Discuss the Seabrook License Renewal Application (CAC No. ME4028) ML16341B9022017-03-0707 March 2017 03/07/2016 Summary of Telecon Held on Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Request for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16342C4672017-03-0101 March 2017 12/01/2016 Summary of Teleconference Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Requests for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16204A2612016-07-29029 July 2016 June 15, 2016 Summary of Pre-Submittal Meeting with NextEra Energy Regarding Proposed License Amendment on Alkali Silica Reaction for the Seabrook Station, Unit No. 1 ML16190A1812016-07-0808 July 2016 Summary of Public Annual Assessment Meeting ML16168A4122016-06-15015 June 2016 Slides for Public Meeting with NextEra Energy Regarding Seabrook Station ASR License Amendment ML16146A1762016-06-0808 June 2016 April 28, 2016, Summary of Public Meeting with NextEra Energy Seabrook, LLC Regarding Aging Management of Alkali-Silica Reaction Pertaining to the License Renewal of Seabrook Station, Unit 1 ML15343A1862016-01-0707 January 2016 License Renewal Call Summary - December 3, 2015 ML15357A3262015-12-23023 December 2015 Memo-Seabrook Conference Call on Dec. 22, 2015-with NextEra Concerning a Request for Additional Information Pertaining to Seabrook Station Operability Determinations for the Alkali-Silica Reaction (ASR)-affected Containment Enclosure Buildi ML15328A1392015-12-0404 December 2015 November 23, 2015, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning Requests for Additional Information Pertaining to the Seabrook Station ML15190A0872015-07-0707 July 2015 June 18, 2015, Summary of Meeting - Seabrook Annual Assessment ML14190B0132014-07-0909 July 2014 June 24, 2014, Summary of Annual Assessment Meeting Regarding Seabrook Station ML14035A2362014-01-30030 January 2014 Seabrook, Unit 1 - Summary of Meeting Between the U.S. Nuclear Regulatory Commission and NextEra Regarding the Status of Alkali-Silica Reaction Testing Program ML13352A5112013-12-27027 December 2013 13-12-18 Seabrook Conference Call Re SAMA RAI 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 ML13158A1972013-06-0707 June 2013 5/30/2013 Summary of Teleconference Between NRC Staff and NextEra Energy Staff Regarding Decommissioning Funding Status Report for Seabrook ML13099A2582013-04-0909 April 2013 3/27/2013: Seabrook - Summary of Annual Assessment Meeting with NextEra Energy 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 ML13004A1782013-01-0404 January 2013 December 11, 2012 Summary of Meeting Regarding Status of Degraded Concrete on Seabrook Station, Unit 1, ML12278A2502012-11-0101 November 2012 Summary of Telephone Conference Call Held Between NRC and NextEra Seabrook, Concerning the RAIs Pertaining to the Seabrook Station, LRA ML12264A6482012-10-16016 October 2012 8/31/2012, Telecon Summary Between NRC and NextEra Seabrook ML12242A5612012-09-18018 September 2012 Summary of Telephone Conference Call Held on August 28, 2012, Between NRC and NextEra Sebrook, LLC, Concerning the Drai Pertaining to the Seabrook, LRA ML12339A2742012-09-13013 September 2012 Concrete Summary 4-12 ML12195A1112012-07-31031 July 2012 Summary of Telephone Conference Call Held on July 3, 2012, Between the NRC and NextEra Energy Seabrook, LLC, Concerning the Draft Request for Additional Information Pertaining to the Seabrook Station, LRA Er ML12165A5952012-06-22022 June 2012 Summary of Telephone Conference Call Held on May 16, 2012, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning the Response to Request for Additional Information Pertaining to the Seabrook Station LRA ML12164A9012012-06-22022 June 2012 Summary of Telephone Conference Call Held on 5/24/12, Between the NRC and NextEra Energy Seabrook, LLC Concerning the Drai Pertaining to the Seabrook Station LRA ML12164A7562012-06-22022 June 2012 Summary of Telephone Conference Call Between NRC and NextEra Seabrook ML12165A7422012-06-21021 June 2012 Summary of Telephone Conference Call Held on April 10, 2012, Between NRC and Energy Seabrook, LLC, Concerning the Response to Request for Additional Information Pertaining to the Seabrook Station LRA ML12142A0422012-05-21021 May 2012 Summary of Public Meeting to Discuss the Nrc'S Annual Assessment of Nextera'S Safety Performance at Seabrook in 2011 ML12054A7662012-03-26026 March 2012 022312, Telecon Summary Between NRC and NextEra Seabrook, Discussing RAIs Response ML12066A1392012-03-20020 March 2012 Summary of Telephone Conference Call Held on March 1, 2012 Between the NRC and NextEra Energy Seabrook Llc., Concerning the Drai Pertaining to the Seabrook Station, LRA Environmental Review 2023-07-11
[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
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Text
License Amendment Request:
Methodology for the Analysis of Concrete Seismic Category I Structures with Concrete Affected by Alkali Silica Reaction Seabrook Station June 15, 2016
NextEra Energy (NYSE: NEE) is comprised of two strong businesses supported by a common platform
- $17B Consolidated Revenues (1)
- 44,900 MW in operation (1, 2)
- One of the largest U.S. electric utilities
- U.S. leader in renewable generation
- Assets primarily in 25 states and Canada
- 19,800 MW in operation (1, 2)
Worlds largest generator of renewable energy from the wind and sun Among Fortunes 2015 list of Worlds Most Admired Companies and among top 10 companies in the world in both the categories of innovativeness and community responsibility Named to 2015 Worlds Most Ethical Company list (Ethisphere Institute)
(1) As of Dec. 31, 2014 from 10-k (2) Includes NEEs ownership share of NextEra Energy Partners portfolio 2
The foundation for everything we do are the Values and Core Principles of our Nuclear Excellence Model 3
Seabrook Attendees
- Ken Browne NEE Seabrook ASR Project Manager
- Mike Ossing NEE Seabrook Licensing Manager
- Brian Brown NEE Seabrook Principal Engineer
- John Simons MPR Gen Manager Power Projects
- Dr. Said Bolourchi SG&H Senior Principal Engineer
- Phil Rush MPR Engineering Associate 4
Presentation Outline
- Overview of License Amendment Request (LAR)
- Structural Capacity Testing of ASR-Affected Specimens
- Evaluation of Structural Deformation
- Monitoring of ASR Expansion and Structure Deformation
-Presentation describes Next Era current intent regarding License Amendment Application 5
Alkali-Silica Reaction 6
Alkali-Silica Reaction
- ASR (alkali-silica reaction) is a chemical reaction between silica from the aggregate (gravel and/or sand) and alkali constituents in the cement
- Reaction produces a gel that expands as it absorbs moisture and exerts a tensile stress from within the concrete K+ gel OH-SiO2 SiO2 forms + H2O SiO2 OH-Na+ gel alkali cement + expansive gel cracking of the reactive aggregate aggregate and paste 7
Overview of License Amendment Request 8
Overview of License Amendment Request
- Next Era proposes a change in the UFSAR methodology to address ASR concrete degradation at Seabrook Station
- ACI 318-71 and the ASME Code do not include provisions for addressing ASR and its effects
- Incorporate loads imposed by ASR into the design basis
- Evaluate structures affected by ASR to demonstrate that they satisfy the acceptance criteria of the original construction code
- ACI 318-71 for all seismic Category I structures other than containment
- ASME Boiler & Pressure Vessel Code,Section III for containment 9
Overview of License Amendment Request
- Applies to Seismic Cat 1 Structures and Containment Structure
- Establish ASR expansion limits from testing:
Shear capacity Flexural capacity and reinforcement development length Anchor bolts embedded in concrete with ASR
- 3 Stage Analysis process for Building Deformation Assessment:
Specify how ASR loads are combined with other design basis loads for analyzing structures including defining load factors Include the effects of concrete creep, shrinkage and swelling in structure deformation analyses Identify ANSYS as the computer code used for ASR building deformation analyses Permit use of the 100-40-40 procedure from Regulatory Guide 1.92, Revision 3 for detailed evaluations (Stage Three) analyses of ASR-affected structures.
Use of cracked section properties and redistribution of self-limiting loads for ASR-affected structures
- Attachments:
UFSAR Markup and Clean Pages MPR 4288, Rev 0 Seabrook Station: Impact of ASR on Structural Design Structural Design Evaluations MPR 4273, Rev 0 Seabrook Station: Implications of Large Scale Test Program Results on Reinforced Concrete Affected by ASR SGH (#TBD) Computation of Load Factors for ASR Demands 10
Structural Capacity Testing of ASR-Affected Specimens 11
Structural Capacity Testing of ASR-Affected Specimens
- MPR conducted large-scale test programs to investigate structural impact of ASR on reinforced concrete
- Improve current understanding of ASR and its effects on reinforced concrete structures
- Evaluate instruments for monitoring (measuring) the through-thickness (out-of-plane) expansion of concrete from ASR 12
Structural Capacity Testing of ASR-Affected Specimens Reinforcement Instrument Anchor Test Shear Test Anchorage Evaluation Program Program Test Program Program Beam Test Programs 13
Structural Capacity Testing of ASR-Affected Specimens Test Program Results Key Conclusion Anchor Test
- Anchor performance No impact on anchors at Program
- insensitive to through-thickness expansion Seabrook based on expansion
- reduces at high levels of in-plane cracking levels expected
- No difference between performance of anchors installed before and after ASR expansion Beam Test
- Control specimens showed consistency with Original design strength and code Programs ACI 318 equations for shear capacity, flexural equations can be used for ASR-capacity and lap splice length affected reinforced concrete structures
- ASR-affected specimens showed:
- No adverse impact of ASR on shear capacity,
- Flexural capacity flexural capacity, reinforcement anchorage and lap
- Reinforcement development length splice performance
- Behavior indicative of pre-stressing due to ASR expansion Instrumentation Snap ring borehole extensometers were accurate Snap ring borehole Evaluation and reliable throughout duration of program extensometers selected for use at Program Seabrook Station 14
Structural Capacity Testing of ASR-Affected Specimens
- Impact on UFSAR Large-scale testing or reinforced-concrete beams showed
- No adverse impact of ASR on shear capacity, flexural capacity or reinforcement development length
- Use of Code equations and design compressive strength to determine capacity is conservative No change to the UFSAR-described methodology is necessary for determining capacity provided ASR expansion is within limits from testing
- ASR expansion limits Expansion limits established based on range of expansion covered in testing Limits to be controlled within Structural Monitoring Program 15
Evaluation of Structural Deformation 16
Evaluation of Structural Deformation
- Inspections of Seabrook structures have identified deformation due to ASR expansion effects
- ASR-related expansion may impose an additional, internal load on reinforced concrete adjacent to ASR-affected areas
- ASR-related expansion of concrete backfill can impose an external load on adjacent structures
- Seismic gap widths and close clearances between structures and plant components may be reduced 17
Methodology for Analysis of Structural Deformation
- LAR describes progressive approach for evaluating structures with deformation
- Stage One - Screening Evaluation
- Stage Two - Analytical Evaluation
- Stage Three - Detailed Evaluation
- Structures require an analysis of all load combinations with ASR loads included 18
Evaluation of Structural Deformation Stage 1: Evaluate Field Screening Observations Responses due to Evaluation ASR loads (Sa)
Original Design Adequate No Stage 2:
Demands & Margin with Analytical Capacities Sa Evaluation Yes Sa = Load associated with ASR Define Threshold for Monitoring 19
Evaluation of Structural Deformation Stage 2: Analytical Evaluation Sa Inputs Based on Finite Correlate with Field Field Measurements and Element Observations other self straining loads Modeling Calculate Sa Stage 3:
Original Design Adequate No Margin with Detailed Demands & Capacities Evaluation Sa Yes Define Threshold for Monitoring 20
Evaluation of Stage 3 Structural Deformation Stage 3: Detailed Evaluation Original Finite Refined Sa Inputs Design Loads Element Based on Additional Inputs Modeling Field Measurements Evaluate Using Total Factored Design Demands Including Sa
- Redistribution of Self-limiting load
- 100-40-40 Combination of seismic components Define Threshold for Monitoring 21
Evaluation of Structural Deformation
- Including ASR loads with other design basis loads requires definition of load factors for each loading combination
- ACI 318-71 and 1975 Edition of ASME B&PV Section III Division 2 does not include load factors for ASR
- SGH developed load factors consistent with ACI 318-71 and ASME 1975 Edition load factor development
- Load factors for ASR will be used in the analysis of Seabrook structures and included in Tables 3.8-1 and 3.8-16 of the UFSAR
- Structures evaluated to demonstrate that additional ASR expansion is permissible
- Margin is included in the acceptance criteria for each stage to ensure that additional deformation does not challenge design limits
- A higher level of deformation is analyzed relative to current measurements to set the threshold for monitoring 22
Evaluation of Structural Deformation
- Stage 2 or Stage 3 evaluation will use an ANSYS finite element model
- Alternate computer codes were used in the original analyses of Seabrook structures
- ANSYS has been used for analyzing safety-related structures in other plant designs (e.g., AP1000, ESBWR)
- NRC has previously accepted the use of ANSYS for structural analysis at other facilities
- Effects of creep, shrinkage, and swelling of concrete must be accounted for in the structure deformation analyses
- Creep, shrinkage and swelling loads are discussed in the Seabrook UFSAR but they were considered negligible in the original design analyses
- ACI 318-71 includes load factors for loads caused by creep, shrinkage and swelling 23
Review of ASR Expansion and Structure Deformation Monitoring 24
Review of ASR Expansion and Structure Deformation Monitoring
- Continued monitoring of ASR and its effects is necessary
- Expansion caused by ASR must be measured and remain bounded by limits established from the large-scale test program
- Periodic measurements of structure deformation are necessary to ensure limits from deformation analyses are satisfied
- Separate monitoring requirements will be included in the Structural Monitoring Program (SMP) for ASR expansion and structure deformation
- SMP uses a three-tiered approach to classify the results of inspections
- ASR expansion levels and structure deformation measurements will be evaluated using classification levels
- Increased monitoring and analysis are necessary for progressively higher levels of ASR expansion and structure deformation 25
Review of ASR Expansion and Structure Deformation Monitoring Typical methods used to measure ASR expansion at Seabrook 26
Review of ASR Expansion and Structures Monitoring Tiers for classifying ASR cracking Recommendation for CRITERIA Structural Monitoring Tier Individual Concrete Combined Cracking Index Program Category Components (CCI)
Unacceptable (requires further 3 Structural Evaluation 1.0 mm/m or greater evaluation)
Quantitative Monitoring and 0.5 mm/m or greater Trending Any area with visual presence of ASR (as defined in FHWA-HIF-2 Acceptable with Deficiencies12-022) accompanied an Qualitative Monitoring estimated summation of crack widths not supporting a 0.5 mm/m CI in the vertical or horizontal direction.
Routine inspection as prescribed Area has no indications of pattern 1 Acceptable by the Structural Monitoring cracking or water ingress- No Program visual presence of ASR
- Limits established in the large-scale test program will be included in the Structural Monitoring Program 27
Review of ASR Expansion and Deformation Monitoring
- Inspection requirements for structures with ASR-induced deformation Stage Deformation Evaluation Stage Monitoring Interval 1D Screening 3 years 2D Analytical 18 months 3D Detailed 6 months
- Parameters that are measured are specific to each structure
- Parameters will be defined in the structure deformation evaluation
- Limits established from deformation evaluation 28
Summary of LAR Changes
- NextEra will submit the following changes to the Seabrook UFSAR:
- ASR expansion loads are taken into account for seismic Category I structures
- Load factors for ASR loads are included in the design load combinations
- Creep, shrinkage and swelling effects are evaluated in the process of analyzing structures with ASR-related deformation
- ANSYS is used for deformation evaluations
- Stage Three deformation evaluations may use 100-40-40 method from NRC Regulatory Guide 1.92, Revision 3, for combining seismic loads instead of the SRSS method in Revision 1 of this regulatory guide.
29
Closing Remarks
- License Amendment Request Represents multiple years of research and learning about ASR
- Third Party Reviews in progress
- Submit to NRC by July 31st 30