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Category:Legal-Pre-Filed Exhibits
MONTHYEARML20010D3712020-01-10010 January 2020 Updated NRC Staff Exhibit List ML19304B3532019-10-31031 October 2019 INT049-R - Supplemental Testimony of Victor E. Saouma, Ph.D Regarding Petrographic Documents ML19262F1292019-09-19019 September 2019 NER005-R2 - NextEra Exhibit List ML19266A6342019-09-0404 September 2019 INT030-R - Rebuttal Testimony of Victor E. Saouma, Ph.D Regarding Scientific Evaluation of Nextera'S Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant (Revised) ML19205A5032019-07-24024 July 2019 NER033 - Matthew Sherman Curriculum Vitae ML19205A5222019-07-24024 July 2019 NER010 - Dr. Oguzhan Bayrak Curriculum Vitae ML19205A5212019-07-24024 July 2019 NER009 - Chris Bagley Curriculum Vitae ML19205A5202019-07-24024 July 2019 NER008 - John Simons Curriculum Vitae ML19205A5182019-07-24024 July 2019 NER048 - L. Phan, Structural Performance of NPP Concrete Structures Affected by Alkali-Silica Reaction (Asr), Slides for NRC Regulatory Information Conference Session TH27 (2018) ML19205A5172019-07-24024 July 2019 NER047 - N. Ezell Et Al., Experimental Collaboration for Thick Concrete Structures with Alkali-Silica Reaction (2018) ML19205A5162019-07-24024 July 2019 NER046 - Seabrook Mechanical Maintenance Procedure MS0517.51, Installation of Geokon Snap-Ring Borehole Extensometers, Rev. 0 (Feb. 2016) (Cover & Pages 13-19) ML19205A5152019-07-24024 July 2019 NER044 - Seabrook Station Unit 1, Updated Final Safety Analysis Report (UFSAR) (Rev. 19) (2.5.2.5 Only) ML19205A5122019-07-24024 July 2019 NER005 - NextEra Exhibit List ML19205A5082019-07-24024 July 2019 NER038 - Gocevski, V., Pathologies/Degradation Mechanisms Experienced by Hydro-Quebec During the Evaluation of Gentilly-2 NPP, Report Submitted to Ascet, (June 2015) ML19205A5052019-07-24024 July 2019 NER035 - U.S. Department of Commerce, National Bureau of Standards, Nbs Special Publication 577, Development of a Probability Based Load Criterion for American National Standard A58 (1980) ML19206A0392019-07-24024 July 2019 NRC070 - Research Activities Fy 2018-2020, NUREG-1925, Rev. 4 (Mar. 2018) ML19205A5022019-07-24024 July 2019 NER032 - Glenn Bell Curriculum Vitae ML19205A5002019-07-24024 July 2019 NER031 - Said Bolourchi Curriculum Vitae ML19205A4972019-07-24024 July 2019 NER028 - Sg&H Report 110594-RPT-02, Rev. 1, Damage Rating Index and ASR Rating (Feb. 10, 2012) (FP100702) ML19205A4962019-07-24024 July 2019 NER027 - Saouma, V., Benchmark Problems for Aar Fea Code Validation (Aug. 4, 2017) ML19205A4952019-07-24024 July 2019 NER018 - MPR-3727, Rev. 1, Seabrook Station: Impact of Alkali-Silica Reaction on Concrete Structures and Attachments (Jan. 2014) and NextEra Supplements I-V Thereto (FP100716, Rev. 4) ML19205A4922019-07-24024 July 2019 NER014 - NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report, Vol. 2 (July 2017) (Cover and Section X.M1) ML19205A4912019-07-24024 July 2019 NER013 - U.S. Department of Transportation, Federal Highway Administration, Report on the Diagnosis, Prognosis, and Mitigation of Alkali-Silica Reaction (ASR) in Transportation Structures (FHWA-HIF-09-004) (Jan. 2010) ML19205A4902019-07-24024 July 2019 NER002 - MPR Testimony - Attachment 1 - Glossary ML19205A4872019-07-24024 July 2019 NRC Staff Appendix a Exhibit List ML19205A4512019-07-24024 July 2019 NRC085 - Letter from William M. Dean, NRC, Kevin Walsh, NextEra, Closure of Confirmatory Action Letter 1-12-002, Seabrook Station, Unit 1 (Oct. 9, 2013) ML19205A4502019-07-24024 July 2019 NRC084 - Letter from Darrell J. Roberts, NRC, to Kevin Walsh, NextEra, Deviation from the Reactor Oversight Process Action Matrix for Seabrook Station, Unit No. 1, (Sept. 12, 2012) ML19205A4492019-07-24024 July 2019 NRC083 - Memorandum from William M. Dean, NRC, to R.W. Borchardt, NRC, Request for Deviation from the Reactor Oversight Process Action Matrix to Provide Increased Oversight of the Alkali-Silica Reaction Issue at Seabrook, (Sept. 5, 2012) ML19205A4482019-07-24024 July 2019 NRC082 - Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Actions for Resolution of Alkali Silica Reaction (ASR) Issues, (May 10, 2012) Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) IR 05000443/20150022019-07-24024 July 2019 NRC031 - Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2015002, (Aug. 5, 2015) IR 05000443/20150042019-07-24024 July 2019 NRC032 - Letter from Fred L. Bower, III, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2015004 and Independent Spent Fuel Storage Installation Report No. 07200063/2015001 (Feb. 12, IR 05000443/20140032019-07-24024 July 2019 NRC029 - Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014003, (Aug. 5, 2014) IR 05000443/20140022019-07-24024 July 2019 NRC028 - Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014002, (May 6, 2014) IR 05000443/20110102019-07-24024 July 2019 NRC024 - Letter from Christopher G. Miller, NRC, to Paul Freeman, NextEra, Seabrook - NRC Inspection Report 05000443/2011010 Related to Alkali-Silica Reaction Issue in Safety Related Structures (Mar. 26, 2012) IR 05000443/20130052019-07-24024 July 2019 NRC027 - Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2013005, (Jan. 30, 2014) IR 05000443/20110022019-07-24024 July 2019 NRC021 - Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit 1 - NRC Integrated Inspection Report 05000443/2011002 (May 12, 2011) IR 05000443/20110032019-07-24024 July 2019 NRC023 - Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2011003 (Aug. 12, 2011) IR 05000443/20170022019-07-24024 July 2019 NRC036 - Letter from Fred L. Bower, III, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2017002, Encl. at 31-32 (Aug. 14, 2017) IR 05000443/20160042019-07-24024 July 2019 NRC035 - Letter from Fred L. Bower, III, NRC, to Eric Mccartney, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2016004, (Feb. 8, 2017) IR 05000443/20160022019-07-24024 July 2019 NRC034 - Letter from to Eric Mccartney, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2016002, (Aug. 5, 2016) IR 05000443/20120102019-07-24024 July 2019 NRC026 - Letter from Raymond K. Lorson, NRC, to Kevin Walsh, Seabrook Station, Unit No. 1 - Confirmatory Action Letter Follow-up Inspection - NRC Inspection Report 05000443/2012010, at 1 (Aug. 9, 2013) IR 05000443/20130062019-07-24024 July 2019 NRC086 - Letter from Darrell J. Roberts, NRC, to Kevin Walsh, NextEra, Mid-cycle Performance Review and Inspection Plan Seabrook Station, Unit 1 (Report 05000443/2013006), (Sept. 3, 2013) ML19205A5232019-07-24024 July 2019 NER011 - Edward Carley Resume IR 05000443/20170042019-07-24024 July 2019 NRC037 - Letter from Fred L. Bower, III, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2017004, Encl. at 24-27 (Feb. 12, 2018) ML19205A4462019-07-24024 July 2019 NRC080 - Memorandum from John G. Lamb, NRC, to Meena Khanna, NRC, Forthcoming Meeting with NextEra Energy Seabrook, LLC (NextEra) Regarding Seabrook Station Concrete Degradation (Mar. 23, 2012) ML19205A4472019-07-24024 July 2019 NRC081 - Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Actions for Resolution of Alkali Silica Reaction (ASR) Issues, (May 3, 2012) IR 05000443/20180012019-07-24024 July 2019 NRC038 - Letter from Fred L. Bower, III, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018001, Encl. at 8-9 (May 14, 2018) IR 05000443/20180112019-07-24024 July 2019 NRC039 - Letter from Mel Gray, III, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018011, (Aug. 10, 2018) IR 05000443/20180032019-07-24024 July 2019 NRC040 - Letter from Fred L. Bower, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018003, (Nov. 13, 2018) 2020-01-10
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD In the Matter of Docket No. 50-443-LA-2 NEXTERA ENERGY SEABROOK, LLC ASLBP No. 17-953-02-LA-BD01 (Seabrook Station, Unit 1)
Hearing Exhibit Exhibit Number: NRC069 Exhibit
Title:
IRSN, ODOBA Research programs, (last update Aug. 2018),
https://www.irsn.fr/EN/Research/Research-organisation/Research-pr ogrammes/Odoba-project/Pages/ODOBA.aspx
7/17/2019 PrintFriendlyEn ODOBA project Last update in August 2018 The ODOBA (Observatory of the durability of reinforced concrete structures) project was launched by IRSN in 2016 for a period of at least 10 years. The aim of the project is to study concrete pathologies and their consequences for nuclear structures (e.g. Reactor containments). The project is led in collaboration with the NRC (Nuclear regulatory authority, US safety authority) , CNSC (Canadian nuclear safety commission), Bel V (Belgian TSO (technical sfety authority)) and VTT (Technical research center of Finland). NSC (Chinese TSO) should soon join the project.
Context and Objectives Nuclear reactors were initially designed to operate for 40 years, but operators, such as EDF, would like to Characteristics extend their service life up to 60 years, and some operators in the United States are even considering up to 80 years. In general, new installations are currently purpose-designed to operate for 60 years, such as the Flamanville EPR, and at least 150 years for the CIGÉO deep geological disposal site, where concrete plays Dates: 2016-2026 a safety and functional role throughout the operating and reversibility phase.
Project partners:
Over such operating periods, concrete can be affected with pathologies resulting from the chemical reactions that take place within it. These pathologies may lead to degradation of the concretes mechanical properties IRSN relies on a network of academic and its ability to ensure the containment of radioactive materials. partners (CONCRETE) for defining the tests and interpreting the data for the Such phenomena have not only been observed on civilian structures (bridges, dams) but also on some ODOBA project:
ENS (Ecole Normale Supérieure ) Paris-nuclear installations: Gentilly-2 in Canada, Seabrook in the United States, Tihange-2 in Belgium, etc. The Saclay, risk of such pathologies developing on the French fleets installations is considered sufficiently credible for specific studies to be launched, of which the ODOBA project. IFSTTAR (Institut Français des Sciences et Technologies des Transports, de lAménagement et des Réseaux, French institute of science and technology for transport, spatial planning, development and networks),
LMA (Laboratoire de Mécanique et Acoustique - Laboratory of Mechanics and Acoustics), University of Aix-Marseille/CNRS, LMDC (Laboratoire Matériaux et Durabilité des Constructions, Building Materials and Sustainability Laboratory), University of Toulouse/INSA Toulouse.
Funding:
Bridge piles affected by a concrete pathology NRC (Nuclear Regulatory Commission), US (Quebec) Chambon Dam (repair following the development of safety authority pathologies) CNSC (Canadian Nuclear Safety Commission), Canadian safety authority BelV, Belgian TSO VTT, Technical Research Center of Finland In 2014 and 2015, the OECD /NEA1 commissioned the ASCET2 working group to assess the extent of knowledge on concrete pathologies and express the needs for improving this knowledge which amounts to:
performing tests on large structures in order to complement the tests usually carried out in small laboratories; studying the combined effects between various pathologies; developing non-destructive testing methods and Involved IRSN laboratories predictive digital tools, etc.
The objectives of the ODOBA project are to meet the following recommendations:
Research Laboratory on the Future of the Radioactive Sites Pollution Better understand the phenomena involved in concrete pathologies and the combinations (LELI) between the various pathologies.
Develop and validate non-destructive testing techniques for early detection of the occurrence of pathologies then monitor their evolution.
https://www.irsn.fr/EN/Print/Pages/PrintFriendlyEn.aspx?wId=0ca8b6bf-624a-4e43-8691-c657100aaefc&iId=5559ea1a-7eab-4098-8034-7cbd8ad79c1 1/3
7/17/2019 PrintFriendlyEn Develop and validate simulation tools for predicting concrete behavior on the structural Research Laboratory for Migration scale. and Interactions in the Geosphere (LETIS) 1 Organisation for economic co-operation and development/Nuclear energy agency Laboratoire de modélisation et 2 Assessment of structures subject to concrete pathologies danalyse de la performance des structures (LMAPS)
Loss of Coolant Accident and Uncertainties Modeling Laboratory (LIMAR)
Experimental Equipment Project workflow Development Laboratory (LR2E)
Environment and Chemistry Experimental Research Laboratory (LE2C)
The ODOBA project mainly involves performing tests on large concrete structures (4 x 2 x 1 m) on IRSN's ODE platform (Observatoire de la Durabilité des Enceintes - Containment durability observatory), located in Mechanics and Materials Cadarache (Bouches-du-Rhne). Some of the concrete blocks will be subjected to accelerated aging Experimental Research Laboratory protocols to simulate long operating periods. (LE2M)
The ODE platform consists of a 1700 m² exterior testing slab that can host up to 60 experimental blocks. It is equipped with equipment for managing the effluents generated by accelerated aging protocols (mineral-laden water). Contact Christophe Marquié ODE platform before casting the first block ODE platform after casting the first 5 blocks The first five blocks were cast in 2016. New blocks will be cast every year as the project progresses and tests are defined by the partners. The various parameters of interest characterizing the test conditions are as follows: nature of the constituents of the concrete, effect of steel reinforcement and pre-stressing, impact of environmental conditions (humidity, CO2 in the air or aquifer, groundwater (e.g. sulfates), conditions with the young age of the concrete (initial weeks after casting), and accelerated aging protocol, etc.
https://www.irsn.fr/EN/Print/Pages/PrintFriendlyEn.aspx?wId=0ca8b6bf-624a-4e43-8691-c657100aaefc&iId=5559ea1a-7eab-4098-8034-7cbd8ad79c1 2/3
7/17/2019 PrintFriendlyEn The following are currently in place or planned:
A reference block without pathologies.
Blocks dedicated to Alkali-silica reaction (ASR): a reaction that occurs between the highly alkaline cement paste and the reactive silica found in certain aggregates.
Blocks dedicated to studying delayed ettringite formation (DEF). This reaction is thermally activated (significant heating of the concrete) within the cement paste.
Blocks for the combined ASR and DEF study.
Blocks dedicated to deep geological disposal facilities: effect of highly saline groundwater.
A block dedicated to the development of non-destructive examination methods.
Twin blocks, with and without steel reinforcement, to characterize the effect of this reinforcement.
The concrete blocks used for the ODOBA project are extensively instrumented in order to obtain various types of data, such as, temperature, humidity, deformation, mechanical stress measurements within the concrete and/or steel reinforcement. The blocks periodically undergo non-destructive and destructive testing to assess changes to the mechanical, physical, micro-structural and chemical properties of the concrete linked with the occurrence and development of pathologies.
Some blocks will be subjected to accelerated aging protocols to reproduce the service life of an installation (40 to 60 years for reactors and up to 150 years for geological disposal facilities) within reasonable time scales (2-3 years). The solution retained involves constructing tanks around the blocks to carry out immersion/drying cycles controlling the temperature and chemistry of the water. The first aging pool will be commissioned in autumn 2018 for qualification prior to deployment on the blocks from 2019.
Given the kinetics of the phenomena, the first results are expected approximately 2 years after casting the blocks.
The results of the ODOBA project will eventually make it possible to develop and validate predictive simulation tools concerning the occurrence and development of pathologies and their consequences on the mechanical and containment properties of concrete on the structural scale. They will also help to assess the non-destructive examination methods.
https://www.irsn.fr/EN/Print/Pages/PrintFriendlyEn.aspx?wId=0ca8b6bf-624a-4e43-8691-c657100aaefc&iId=5559ea1a-7eab-4098-8034-7cbd8ad79c1 3/3