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Category:Note
MONTHYEARML12174A0872011-12-20020 December 2011 Concrete Degradation - Region I Engineering Branch No. 1 (Eb 1); Seabrook Concrete Degradation & Implications to Part 50 & 54, December 20 2011, 2:00 Pm, W/Handwritten Notes ML12054A7012011-08-0101 August 2011 E-mail from Rich Conte, Region I to Rich Conte, Region I; Subject: Cliffords Comments on TIA Draft 5 FW: Message from R1-2019K501, W/Handwritten Notes ML12054A6412011-05-24024 May 2011 Concrete Degradation - Alkali Silica Reaction, W/Handwritten Notes 2011-08-01
[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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Seabrook Concrete Degradation -
Alkali Silica Reaction May 24, 2011 Lead: Ed 1
Alkali-Silica Reaction (ASR)
" Occurs over time in concrete between alkaline cement paste and reactive non-crystalline silica found in common coarse aggregates
" Requires susceptible aggregate and adequate moisture
- Forms a gel that expands and causes microcrack network
" Changes strength of reinforced concrete; reduces stiffness 2
Lead: Bryce/Abd.ul Provide Pictures Of ASR Examples v' ~~/tfU~
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2
Background
" June 2009 - Licensee begins walkdowns as part of license renewal application preparation; groundwater leakage and extensive cracking of concrete in different plant areas
" April to June 2010 - Licensee tests concrete including penetration resistance testing and 12 concrete cores from affected areas in 'B' Electric Tunnel which showed significant reduction in compressive strength and modulus of elasticity
" August 2010 - Petrographic examination of concrete cores confirms presence of ASR
" September 2010 - Licensee completes prompt operability determination concluding structures are operable 3
Lead: Ed Provide Remaining Pictures 3
Background (Cont.)
" September 2010 - Licensee issues a design change package to reflect the reduction in strength and modulus of elasticity in the plant licensing basis
" October 2010 - During license renewal audit, NRC staff identified 6 feet of water in containment annulus region
- When water removed, patterned cracking indicative of ASR identified on both primary containment and containment enclosure building
" May 2011 - Licensee takes concrete cores from 5 additional areas
- Results of core testing are pending 4
Lead: Ed 4
Problem Summary
" Below-grade concrete structures experiencing groundwater infiltration.
" Aging management review found degraded conditions in below-grade areas for several structures
" Degradation mechanism identified as or suspected to be ASR
- First nuclear plant in U.S. to experience ASR Lead: Ed 5
Current Status
- NRC overseeing licensee actions and engaging in development of the final operability determination Quarterly resident report issued May 12, 2011
- NCV green) on failure to adequately monitor the control building for the recent Clegra aion
- NOV (green) on failure to include transition buildings as in-scope structures in Maintenance Rule monitoring program
- Design basis not exceeded based on licensee operability determination License Renewal Inspection report issued May 23, 2011
- Report noted that the aging management review for the ASR issue is incomplete DE, DLR, DORL and Region I are working together to successfully resolve this issue with respect to Parts 50 and 54 6
Lead: Meena A-1 U A IIY) /
6
Licensee's Prompt Operability Determination
" Structural integrity of the Control Building was intact
- All systems and components housed within the building were operable and capable of performing their design function
" ASR has resulted in reduction of elastic modulus of concrete and compressive strength in portions of below grade walls
" Developing a comprehensive test and evaluation plan to manage ASR 7
Lead: Meena 7
Licensee Ongoing Actions Extent of Condition and Root Cause Review
- Operability determination on buildings associated with extent of condition review
- Apparent root cause review for the 10 CFR 50.65 violations
- Continuing root cause evaluation related to ASR issue
- Periodic operability assessments as information is developed for the aging management review will be completed Lead: Meena 8
NRC Staff Ongoing Actions (Seabrook Specific)
Region I preparing a Task Interface Agreement (TIA) to request support from NRR
- Design change
- Final Operability determination DE, DLR, DORL and Region I continue to work together to address this issue with respect to both Parts 50 and 54 This issue is currently tracked as an Open Item in the upcoming license renewal SER Lead: Ed While we don't disagree with the supporting information provided by the licensee
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NRC Staff Ongoing Actions (Generic)
Preparing generic communication (IN) to inform other licensees about the ASR potential in plants with groundwater leakage; expected issuance next quarter Operating Experience group has issued an internal communication and continues to follow the issue for generic applicability 10 Lead: Ed 10
ASR on One of the Walls
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Microscopic Example of ASR 2
Seabrook Station Plan LOCATIONS CORE CONCRETE DIESELCOTL GENERATOR BUILDING BUILDING RCAWALKWAY i r' L VAULT*.
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~~STRUCTUREml 4-FT THICK44, WAT TANK PRIMARY WAPTE BUILDING FARM AUX BLDfhmG ARAENCLOSUIRE CONCRETE BUILDING
... 30-IN THICK 3
Seabrook .Containment and Enclosure Building -Cracking 4
Seabrook Electrical Tunnel 5