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{{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges: | {{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges: | ||
Ronald M. Spritzer, Chairman Nicholas G. Trikouros Dr. Sekazi K. Mtingwa In the Matter of | Ronald M. Spritzer, Chairman Nicholas G. Trikouros Dr. Sekazi K. Mtingwa In the Matter of NEXTERA ENERGY SEABROOK, LLC (Seabrook Station, Unit 1) | ||
On August 12, 2019, the Board issued an order to schedule a prehearing teleconference with all the parties to discuss logistics for the evidentiary hearing planned for September 24-27, 2019. The order contained a list of discussion topics and stated that the Board would prepare a final exhibit list identifying all pre-filed testimony and other exhibits (including revised exhibits) that have been filed by the participants. 1 During the prehearing teleconference on August 26, 2019, the Board again stated that it would prepare a final exhibit list. This list is now attached as Appendix A. | Docket No. 50-443-LA-2 ASLBP No. 17-953-02-LA-BD01 August 27, 2019 MEMORANDUM (Regarding Pre-filed Exhibits) | ||
On August 12, 2019, the Board issued an order to schedule a prehearing teleconference with all the parties to discuss logistics for the evidentiary hearing planned for September 24-27, 2019. The order contained a list of discussion topics and stated that the Board would prepare a final exhibit list identifying all pre-filed testimony and other exhibits (including revised exhibits) that have been filed by the participants.1 During the prehearing teleconference on August 26, 2019, the Board again stated that it would prepare a final exhibit list. This list is now attached as Appendix A. | |||
The Board also notes that numerous prefiled exhibits contain references to documents that have not been filed in the evidentiary record. If any party desires the documentary material, website material, or incorporated reports cited in these pre-filed exhibits to be considered part of the evidentiary record, the party should promptly provide a PDF evidentiary exhibit of each item, 1 Order (Scheduling Prehearing Teleconference) at 3 (Aug. 12, 2019) (unpublished). | The Board also notes that numerous prefiled exhibits contain references to documents that have not been filed in the evidentiary record. If any party desires the documentary material, website material, or incorporated reports cited in these pre-filed exhibits to be considered part of the evidentiary record, the party should promptly provide a PDF evidentiary exhibit of each item, 1 Order (Scheduling Prehearing Teleconference) at 3 (Aug. 12, 2019) (unpublished). | ||
or the relevant portions thereof, with an appropriate exhibit cover sheet and an updated exhibit list. | or the relevant portions thereof, with an appropriate exhibit cover sheet and an updated exhibit list. | ||
FOR THE ATOMIC SAFETY AND LICENSING BOARD | FOR THE ATOMIC SAFETY AND LICENSING BOARD Ronald M. Spritzer, Chairman ADMINISTRATIVE JUDGE Rockville, Maryland August 27, 2019 | ||
/RA/ | |||
Ronald M. Spritzer, Chairman ADMINISTRATIVE JUDGE Rockville, Maryland August 27, 2019 | |||
APPENDIX A: LIST OF PREFILED EXHIBITS IN THE MATTER OF NEXTERA ENERGY SEABROOK, LLC, (SEABROOK STATION, UNIT 1) | APPENDIX A: LIST OF PREFILED EXHIBITS IN THE MATTER OF NEXTERA ENERGY SEABROOK, LLC, (SEABROOK STATION, UNIT 1) | ||
DOCKET NO. 50-443-LA- | DOCKET NO. 50-443-LA-22 NRC Staff Exhibits Exhibit Number Title NRC-001 Staff Testimony. | ||
NRC-002 | NRC-002 Statement of Professional Qualifications of Angela Buford. | ||
NRC-003 | NRC-003 Statement of Professional Qualifications of Bryce Lehman. | ||
NRC-004 | NRC-004 Statement of Professional Qualifications of George Thomas. | ||
NRC-005 | NRC-005 Jacob Philip Testimony. | ||
NRC-006 | NRC-006 Statement of Professional Qualifications of Jacob Philip. | ||
NRC-007 | NRC-007 Seabrook Station Updated Final Safety Analysis Report (UFSAR), | ||
Chapter 3, "Design of Structures, Components, Equipment and Systems, Revision 18 (October 2017). | Chapter 3, "Design of Structures, Components, Equipment and Systems, Revision 18 (October 2017). | ||
NRC-008 | NRC-008 to Original LAR, MPR-4273, Revision 0, Seabrook Station - | ||
Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016). | Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016). | ||
NRC-009 | NRC-009 to Original LAR, MPR-4273, Revision 0, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016) | ||
(proprietary). | (proprietary). | ||
NRC-010 | NRC-010 Letter from Ralph A. Dodds III, NextEra, to NRC Document Control Desk, Seabrook Station, Supplement to License Amendment Request 16-03, Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction (Sept. 30, 2016). | ||
NRC-011 | NRC-011 to Sept. 2016 LAR Supplement, MPR-4153, Revision 2, Seabrook Station - Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction (July 2016). | ||
2 Exhibits containing proprietary information are so identified and highlighted in bold. | 2 Exhibits containing proprietary information are so identified and highlighted in bold. | ||
NRC-012 to Sept. 2016 LAR Supplement, Revision 2, MPR-4153, Rev. 2, Seabrook Station - Approach for Determining Through Thickness Expansion from Alkali-Silica Reaction (July 2016) | |||
NRC-012 | |||
(proprietary). | (proprietary). | ||
NRC-013 Letter from Eric McCartney, NextEra, to NRC Document Control Desk, Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (Oct. 3, 2017). | NRC-013 Letter from Eric McCartney, NextEra, to NRC Document Control Desk, Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (Oct. 3, 2017). | ||
| Line 52: | Line 49: | ||
ME4028) (Dec. 17, 2015). | ME4028) (Dec. 17, 2015). | ||
NRC-018 Seabrook ASR-Monitoring Program Audit Report, Enclosure to Dec. 17, 2015 Letter to NextEra (undated). | NRC-018 Seabrook ASR-Monitoring Program Audit Report, Enclosure to Dec. 17, 2015 Letter to NextEra (undated). | ||
Confirmatory Action Letter, Seabrook Station, Unit 1 - Information | NRC-019 Confirmatory Action Letter, Seabrook Station, Unit 1 - Information Related to Concrete Degradation Issues (May 16, 2012). | ||
Letter from Richard A. Plasse, NRC, to Paul Freeman, NextEra, Audit | NRC-020 Letter from Richard A. Plasse, NRC, to Paul Freeman, NextEra, Audit Report Regarding the Seabrook Station License Renewal Application (TAC Number ME4028) (Mar. 21, 2011). | ||
Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook | NRC-021 Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2011002 (May 12, 2011). | ||
Letter from Richard J. Conte, NRC, to Paul Freeman, NextEra, NextEra | NRC-022 Letter from Richard J. Conte, NRC, to Paul Freeman, NextEra, NextEra Energy Seabrook - NRC License Renewal Inspection Report 05000443/2011007 (May 23, 2011). | ||
Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook | NRC-023 Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2011003 (Aug. 12, 2011). | ||
Letter from Christopher G. Miller, NRC, to Paul Freeman, NextEra, Seabrook Station - NRC Inspection Report 05000443/2011010 Related | NRC-024 Letter from Christopher G. Miller, NRC, to Paul Freeman, NextEra, Seabrook Station - NRC Inspection Report 05000443/2011010 Related to Alkali-Silica Reaction Issue In Safety Related Structures (Mar. 26, 2012). | ||
NRC-025 Letter from Christopher G. Miller, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - Confirmatory Action Letter Follow-up Inspection - NRC Inspection Report 05000443/2012009, Enclosure, Inspection Report No. 0500044312012009 (Dec. 3, 2012). | |||
Letter from Christopher G. Miller, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - Confirmatory Action Letter Follow-up | NRC-026 Letter from Raymond K. Lorson, NRC, to Kevin Walsh, Seabrook Station, Unit No. 1 - Confirmatory Action Letter Follow-up Inspection - | ||
Letter from Raymond K. Lorson, NRC, to Kevin Walsh, Seabrook | |||
NRC Inspection Report 05000443/2012010 (Aug. 9, 2013). | NRC Inspection Report 05000443/2012010 (Aug. 9, 2013). | ||
Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook | NRC-027 Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2013005 (Jan. 30, 2014). | ||
Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook | NRC-028 Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014002 (May 6, 2014). | ||
Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook | NRC-029 Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014003 (Aug. 5, 2014). | ||
Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook | NRC-030 Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014005, (Feb. 6, 2015). | ||
Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook | NRC-031 Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2015002, (Aug. 5, 2015). | ||
Letter from Fred L. Bower, III, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report | NRC-032 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, 2016). | ||
Letter from Mel Gray, NRC, to Dean Curtland, NextEra, Seabrook Station, Seabrook Station - Inspection Report 05000443/2016008 | NRC-033 Letter from Mel Gray, NRC, to Dean Curtland, NextEra, Seabrook Station, Seabrook Station - Inspection Report 05000443/2016008 Related to Alkali-Silica Reaction Affects On Safety-Related Concrete Structures And Notice Of Violation, (May 6, 2016). | ||
Letter from to Eric McCartney, NextEra, Seabrook Station, Unit No. 1 - | NRC-034 Letter from to Eric McCartney, NextEra, Seabrook Station, Unit No. 1 - | ||
Integrated Inspection Report 05000443/2016002, (Aug. 5, 2016). | |||
Letter from Fred L. Bower, III, NRC, to Eric McCartney, NextEra, | NRC-035 Letter from Fred L. Bower, III, NRC, to Eric McCartney, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2016004, (Feb. 8, 2017). | ||
Letter from Fred L. Bower, III, NRC, to Mano Nazar, NextEra, Seabrook | NRC-036 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). | ||
Letter from Fred L. Bower, III, NRC, to Mano Nazar, NextEra, Seabrook | NRC-037 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). | ||
NRC-038 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). | |||
Letter from Fred L. Bower, III, NRC, to Mano Nazar, NextEra, Seabrook | NRC-039 Letter from Mel Gray, III, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018011, (Aug. 10, 2018). | ||
Letter from Mel Gray, III, NRC, to Mano Nazar, NextEra, Seabrook | NRC-040 Letter from Fred L. Bower, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018003, (Nov. 13, 2018). | ||
Letter from Fred L. Bower, NRC, to Mano Nazar, NextEra, Seabrook | NRC-041 Letter from Richard Plasse, NRC, to Kevin Walsh, NextEra, Aging Management Program Audit Report Regarding the Seabrook Station License Renewal Application (TAC No. ME4028) (Dec. 23, 2013). | ||
Letter from Richard Plasse, NRC, to Kevin Walsh, NextEra, Aging | NRC-042 Letter from Tam Tran, NRC, to Eric McCartney, NextEra, Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal (CAC No. | ||
Letter from Tam Tran, NRC, to Eric McCartney, NextEra, Alkali Silica Reaction Monitoring Aging Management Program Audit Report | |||
ME4028) (Dec. 21, 2016). | ME4028) (Dec. 21, 2016). | ||
Letter from Justin C. Poole, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali-Silica Reaction License | NRC-043 Letter from Justin C. Poole, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali-Silica Reaction License Amendment Request and License Renewal Alkali-Silica Reaction Aging Management Program Review (CAC No. MF8260; EPID L-2016-LLA-0007) (July 26, 2017). | ||
Letter from Justin C. Poole, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali-Silica Reaction License | NRC-044 Letter from Justin C. Poole, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali-Silica Reaction License Amendment Request and License Renewal Alkali-Silica Reaction Aging Management Program Review (CAC No. MF8260; EPID L-2016-LLA-0007) (May 21, 2018). | ||
Memorandum from Eric J. Leeds, NRR, and William M. Dean, Region 1, | NRC-045 Memorandum from Eric J. Leeds, NRR, and William M. Dean, Region 1, Seabrook Alkali-Silica Reaction Issue Technical Team Charter (July 9, 2012). | ||
Summary of August 24, 2017, Meeting with NextEra Energy Regarding | NRC-046 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) (Oct. 13, 2017). | ||
Memorandum from James G. Danna, NRC, to Andrea D. Veil, NRC ACRS, Seabrook Station, Unit No. 1 - Submission of Alkali-Silica Reaction License Amendment Request Draft Safety Evaluation to | NRC-047 Memorandum from James G. Danna, NRC, to Andrea D. Veil, NRC ACRS, Seabrook Station, Unit No. 1 - Submission of Alkali-Silica Reaction License Amendment Request Draft Safety Evaluation to Support the Advisory Committee on Reactor Safeguards Review of Seabrook License Renewal (CAC No. MF8260; EPID L-2016-LLA-0007) | ||
(Sept. 28, 2018). | (Sept. 28, 2018). | ||
Letter from Michael Corradini, Chairman, ACRS, to Kristine L. Svinicki, Chairman, NRC, Seabrook Station Unit 1 License Renewal Application: | NRC-048 Letter from Michael Corradini, Chairman, ACRS, to Kristine L. Svinicki, Chairman, NRC, Seabrook Station Unit 1 License Renewal Application: | ||
Review of Licensee Program Addressing Alkali-Silica Reaction (Dec. 14, 2018). | |||
NRC-049 American Concrete Institute (ACI) Standard 318-71, Building Code Requirements for Reinforced Concrete (1971). | |||
American Concrete Institute (ACI) Standard 318-71, Building Code | NRC-050 Section Ill, Division 2, of the 1975 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for containment. | ||
Section Ill, Division 2, of the 1975 Edition of the American Society of | NRC-051 Report of ACI-ASCE (American Society of Civil Engineers) Committee 326, Shear and Diagonal Tension (1962). | ||
Report of ACI-ASCE (American Society of Civil Engineers) Committee | NRC-052 ACI 408R-03, Bond and Development of Straight Reinforcing Bars in Tension (effective Sept. 24, 2003) (reapproved 2012). | ||
ACI 408R-03, Bond and Development of Straight Reinforcing | NRC-053 Letter from Public Service Company of New Hampshire to NRC Region I, Office of Inspection and Enforcement re: Response to NRC IE Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts, Revision 2, November 8, 1979 (Jan 3. 1980). | ||
Letter from Public Service Company of New Hampshire to NRC Region I, Office of Inspection and Enforcement re: Response to NRC IE Bulletin | NRC-054 NUREG/CR-5563, A Technical Basis for Revision to Anchorage Criteria, March 1999. | ||
NUREG/CR-5563, A Technical Basis for Revision to Anchorage | NRC-055 ACI 349-13, Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary 2013. | ||
ACI 349-13, Code Requirements for Nuclear Safety-Related Concrete | NRC-056 Madhu M. Karthik, et. al., Experimental Behavior of Large Reinforced Concrete Specimen with Heavy ASR and DEF [delayed ettringite formation] Deterioration, J. Struct. Eng. (2018) (published online May 31, 2018). | ||
Madhu M. Karthik, et. al., Experimental Behavior of Large Reinforced Concrete Specimen with Heavy ASR and DEF [delayed | NRC-057 M. Kathleen Eck Olave, et. al., Performance of RC Columns Affected by ASR. II: Experiments and Assessment, Vol. 20. ASCE J. of Bridge Engg (March 2015) (published online June 12, 2014). | ||
M. Kathleen Eck Olave, et. al., Performance of RC Columns Affected by | NRC-058 F. Habibi, et. al., Alkali Aggregate Reaction in Nuclear Concrete Structures: Part 3: Structural Shear Wall Elements, Transactions, 23rd Conference on Structural Mechanics in Reactor Technology (SMiRT-23), | ||
F. Habibi, et. al., Alkali Aggregate Reaction in Nuclear Concrete Structures: Part 3: Structural Shear Wall Elements, Transactions, 23rd | |||
Manchester, UK, August 10-14, 2015, Division I, Paper ID 044. | Manchester, UK, August 10-14, 2015, Division I, Paper ID 044. | ||
ACI 349.3R, Evaluation of Existing Nuclear Safety-Related Concrete | NRC-059 ACI 349.3R, Evaluation of Existing Nuclear Safety-Related Concrete Structures (2002) (Reapproved 2010). | ||
NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica | NRC-060 NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011). | ||
Standard Review Plan for Review of Subsequent License Renewal | NRC-061 Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants (Final Report), NUREG-2192 (July 2017). | ||
NRC-062 Interagency Agreement between NRC and NIST (Mar. 31, 2014). | NRC-062 Interagency Agreement between NRC and NIST (Mar. 31, 2014). | ||
Grant and Cooperative Agreement between NRC and Northwestern | NRC-063 Grant and Cooperative Agreement between NRC and Northwestern University (Sept. 30, 2014). | ||
NRC-064 Sherry Berhoft, EPRI Senior Program Manager, NRC Commissioner Briefing on the Status of Subsequent License Renewal Preparations, EPRI Long Term Operations: Research & Development for Aging Management (Apr. 26, 2017). | |||
Sherry Berhoft, EPRI Senior Program Manager, NRC Commissioner Briefing on the Status of Subsequent License Renewal Preparations, | NRC-065 Emma L. Wong & Sherry Bernhoft, Overview of the Electric Power Research Institutes Research for Long Term Operations, 117 Transactions of the Am. Nuclear Socy, 648, 648 (Oct. 29-Nov. 2, 2017). | ||
Emma L. Wong & Sherry Bernhoft, Overview of the Electric Power Research Institutes Research for Long Term Operations, 117 | NRC-066 U.S. Department of Energy, Light Water Reactor Sustainability Program A Summary of Collaborative Research and Development Activities, INL/EXT-19-52416, Rev. 0 (Jan. 2019). | ||
U.S. Department of Energy, Light Water Reactor Sustainability Program | NRC-067 Organisation for Economic Cooperation and Development, Nuclear Energy Agency, Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies NEA/CSNI/R(2016)13 (July 2017). | ||
Organisation for Economic Cooperation and Development, Nuclear Energy Agency, Final Report on the Phase 1 of the Assessment of | NRC-068 Organisation for Economic Cooperation and Development, Nuclear Energy Agency, Phase II of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report NEA/CSNI/R(2018)4 (Jan. | ||
Organisation for Economic Cooperation and Development, Nuclear Energy Agency, Phase II of the Assessment of Structures Subjected to | |||
21, 2019). | 21, 2019). | ||
IRSN, ODOBA Research programs, (last update Aug. 2018), | NRC-069 IRSN, ODOBA Research programs, (last update Aug. 2018), | ||
https://www.irsn.fr/EN/Research/Research-organisation/Research-programmes/Odoba-project/Pages/ODOBA.aspx. | |||
NRC-070 Research Activities FY 2018-2020, NUREG-1925, Rev. 4 (Mar. 2018). | NRC-070 Research Activities FY 2018-2020, NUREG-1925, Rev. 4 (Mar. 2018). | ||
NUREG/CR-7153, Expanded Materials Degradation Assessment | NRC-071 NUREG/CR-7153, Expanded Materials Degradation Assessment (EMDA), Volume 4: Aging of Concrete and Civil Structures (Oct. 2014). | ||
R. Park and T. Paulay, Reinforced Concrete Structures (John Wiley & | NRC-072 R. Park and T. Paulay, Reinforced Concrete Structures (John Wiley & | ||
Sons, Inc. 1975). | |||
David Darwin, Charles W. Dolan, and Arthur H. Nilson, Design of | NRC-073 David Darwin, Charles W. Dolan, and Arthur H. Nilson, Design of Concrete Structures (McGraw Hill, Inc., 15th Ed. 2016). | ||
Stéphane Multon, et. al., Flexural Strength of Beams Affected by | NRC-074 Stéphane Multon, et. al., Flexural Strength of Beams Affected by ASR, 12th International Conference on Alkali-Aggregate Reaction, Beijing, China (2004). | ||
Dean J., Deschenes, et. al., ASR/DEF-Damaged Bent Caps: Shear Tests and Field Implications, Technical Report No. 12-8XXIA006 | NRC-075 Dean J., Deschenes, et. al., ASR/DEF-Damaged Bent Caps: Shear Tests and Field Implications, Technical Report No. 12-8XXIA006 summarizing work conducted for the Texas Department of Transportation at Ferguson Structural Engineering Laboratory, The University of Texas at Austin (August 2009). | ||
Canadian Standards Association (CSA) A864-00, Guide to the | NRC-076 Canadian Standards Association (CSA) A864-00, Guide to the Evaluation and Management of Concrete Structures Affected by Alkali-Aggregate Reaction (Feb. 2000) (Reaffirmed 2005). | ||
NRC-077 Geoffrey E. Blight and Mark G. Alexander, Alkali-Aggregate Reaction and Structural Damage to Concrete - Engineering Assessment, Repair and Management, (CRC Press Taylor & Francis Group, 2011). | |||
Geoffrey E. Blight and Mark G. Alexander, Alkali-Aggregate | NRC-078 Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Response to Confirmatory Action Letter (May 24, 2012). | ||
Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station | NRC-079 to SBK-L-12106, The Evaluation, Impact of ASR on Concrete Structures and Attachments, (May 2012) (Interim Structural Assessment). | ||
NRC-080 Memorandum from John G. Lamb, NRC, to Meena Khanna, NRC, Forthcoming April 23, 2012 Meeting with NextEra Energy Seabrook, LLC (NextEra) Regarding Seabrook Station Concrete Degradation (Mar. 23, 2012). | |||
Memorandum from John G. Lamb, NRC, to Meena Khanna, NRC, Forthcoming April 23, 2012 Meeting with NextEra Energy Seabrook, LLC | NRC-081 Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Actions for Resolution of Alkali Silica Reaction (ASR) Issues (May 3, 2012). | ||
Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station | NRC-082 Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Supplement to Actions for Resolution of Alkali Silica Reaction (ASR) | ||
Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station | |||
Issues (May 10, 2012). | Issues (May 10, 2012). | ||
Memorandum from William M. Dean, NRC, to R.W. Borchardt, NRC, Request for Deviation from the Reactor Oversight Process Action Matrix | NRC-083 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). | ||
Letter from Darrell J. Roberts, NRC, to Kevin Walsh, NextEra, Deviation | NRC-084 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). | ||
Letter from William M. Dean, NRC, Kevin Walsh, NextEra, Closure of | NRC-085 Letter from William M. Dean, NRC, Kevin Walsh, NextEra, Closure of Confirmatory Action Letter 1-12-002, Seabrook Station, Unit 1 (Oct. 9, 2013). | ||
Letter from Darrell J. Roberts, NRC, to Kevin Walsh, NextEra, Mid-cycle | NRC-086 Letter from Darrell J. Roberts, NRC, to Kevin Walsh, NextEra, Mid-cycle Performance Review and Inspection Plan - Seabrook Station, Unit No. 1 (Report 05000443/2013006), (Sept. 3, 2013). | ||
Email from Justin Poole, NRC, to Kenneth Browne, NextEra, Audit Plan | NRC-087 Email from Justin Poole, NRC, to Kenneth Browne, NextEra, Audit Plan Regarding Seabrook ASR License Amendment Review, (Jan. 13, 2017). | ||
Regulatory Guide (RG) 1.29, Seismic Design Classification for Nuclear | NRC-088 Regulatory Guide (RG) 1.29, Seismic Design Classification for Nuclear Power Plants (July 2016). | ||
NRC-089 to Original LAR, NextEra Energy Seabrook's Evaluation of the Proposed Change Including Attachment 1 Markup of UFSAR Pages (proprietary). | |||
NextEra Exhibits Exhibit Number Title NER-001 Testimony of NextEra Witnesses Michael Collins, John Simons, Christopher Bagley, Oguzhan Bayrak, and Edward Carley (MPR Testimony). | |||
NextEra Exhibits Exhibit Number | NER-002 MPR Testimony - Attachment 1 - Glossary. | ||
NER-002 | NER-003 MPR Testimony - Attachment 2 - Proprietary Appendix. | ||
NER-003 | NER-004 Testimony of NextEra Witnesses Said Bolourchi, Glenn Bell, and Matthew Sherman (SGH Testimony). | ||
Testimony of NextEra Witnesses Said Bolourchi, Glenn Bell, and | NER-005 NextEra Exhibit List. | ||
NER-005 | NER-006 Michael Collins Biography. | ||
NER-006 | NER-007 Seabrook Structures Monitoring Program Manual, Rev. 7 (proprietary). | ||
Seabrook Structures Monitoring Program Manual, Rev. | NER-008 John Simons Curriculum Vitae. | ||
NER-008 | NER-009 Chris Bagley Curriculum Vitae. | ||
NER-009 | NER-010 Dr. Oguzhan Bayrak Curriculum Vitae. | ||
NER-010 | NER-011 Edward Carley Resume. | ||
NER-011 | NER-012 The Institution of Structural Engineers, Structural Effects of Alkali-Silica Reaction (July 1992). | ||
The Institution of Structural Engineers, Structural Effects of | NER-013 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. | ||
U.S. Department of Transportation, Federal Highway Administration, Report on the Diagnosis, Prognosis, and Mitigation of Alkali-Silica | |||
2010). | 2010). | ||
NUREG-2191, Generic Aging Lessons Learned for Subsequent | NER-014 NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report, Vol. 2 (July 2017) [Cover and Section X.M1]. | ||
MPR-3848, Rev. 0 Seabrook Station, Approach for Shear and | NER-015 MPR-3848, Rev. 0 Seabrook Station, Approach for Shear and Reinforcement Anchorage Testing of Concrete Affected by Alkali-Silica Reaction (Apr. 2013) (FP100818) (proprietary). | ||
NER-016 Allford, M., Expansion Behavior of Reinforced Concrete Elements Due to Alkali-Silica Reaction (Aug. 2016). | |||
Allford, M., Expansion Behavior of Reinforced Concrete Elements Due | NER-017 EPRI Report 3002013192, Evaluation of Laboratory Tests to Detect Up-to-Date Expansion and Remaining Expansion in Concrete Structures Affected by Alkali-Silica Reaction (Oct. 15, 2018). | ||
EPRI Report 3002013192, Evaluation of Laboratory Tests to Detect Up- | NER-018 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). | ||
MPR-3727, Rev. 1, Seabrook Station: Impact of Alkali-Silica Reaction on | NER-019 Bayrak, O., Structural Implications of ASR; State of the Art (Feb. | ||
Bayrak, O., Structural Implications of ASR; State of the Art (Feb. | 2, 2012) (FP100697) (proprietary). | ||
NER-020 MPR 0326-0062-88, Rev. 2, Initial Expansion Assessment of ASR Affected Reinforced Concrete Structures at Seabrook Station (Mar. 2018) (FP101070, Rev. 1) (proprietary). | |||
MPR 0326-0062-88, Rev. 2, Initial Expansion Assessment of ASR | NER-021 MPR-4231, Rev. 0, Instrumentation for Measuring Expansion in Concrete Affected by Alkali-Silica Reaction (Oct. 2015) (FP100972) | ||
MPR-4231, Rev. 0, Instrumentation for Measuring Expansion in | |||
(proprietary). | (proprietary). | ||
MPR-4262, Shear and Reinforcement Anchorage Testing of Concrete Affected by Alkali- Silica Reaction, Vol. I, Rev. 1 (July | NER-022 MPR-4262, Shear and Reinforcement Anchorage Testing of Concrete Affected by Alkali-Silica Reaction, Vol. I, Rev. 1 (July 2016) & Vol. II, Rev. 0 (Jan. 2016) (FP100994) [Main Report & Apps. E | ||
& G] (proprietary). | |||
MPR-3722, Rev. 2, Strength Testing of Anchors in Concrete | NER-023 MPR-3722, Rev. 2, Strength Testing of Anchors in Concrete Affected by Alkali-Silica Reaction (Jan. 2016) (FP100718, Rev. 1) | ||
[Main Report & App. A] (proprietary). | [Main Report & App. A] (proprietary). | ||
MPR-4247, Rev. 0 Commercial Grade Dedication Report for Seabrook ASR Anchor Testing (Block Series and Girder Series | NER-024 MPR-4247, Rev. 0 Commercial Grade Dedication Report for Seabrook ASR Anchor Testing (Block Series and Girder Series Phase 2) (Dec. 2015) (FP100986) [Main Report & Apps. A & B] | ||
(proprietary). | (proprietary). | ||
MPR-4259, Commercial Grade Dedication Report of Seabrook ASR Shear, Reinforcement Anchorage and Instrumentation Testing | NER-025 MPR-4259, Commercial Grade Dedication Report of Seabrook ASR Shear, Reinforcement Anchorage and Instrumentation Testing (Jan. 2016) [Main Report, App. B, & Pages D-1745, D-2615 to 16, F-9474, G-14, and G-18 to 19] (proprietary). | ||
MPR-3757, Rev. 4, Shear and Reinforcement Anchorage Test | NER-026 MPR-3757, Rev. 4, Shear and Reinforcement Anchorage Test Specimen Technical Evaluation (May 2014) (FP100760) | ||
(proprietary). | (proprietary). | ||
Saouma, V., Benchmark Problems for AAR FEA Code Validation (Aug. | NER-027 Saouma, V., Benchmark Problems for AAR FEA Code Validation (Aug. | ||
4, 2017). | |||
SG&H Report 110594-RPT-02, Rev. 1, Damage Rating Index and ASR | NER-028 SG&H Report 110594-RPT-02, Rev. 1, Damage Rating Index and ASR Rating (Feb. 10, 2012) (FP100702). | ||
EPRI Report 3002013190, Modeling Concrete Structures Affected by | NER-029 EPRI Report 3002013190, Modeling Concrete Structures Affected by Alkali Silica Reaction: Hydro-Quebec Approach for Hydraulic and Nuclear Power Plants (Oct. 15, 2018). | ||
NER-030 Giannini, E., Evaluation of Concrete Structures Affected by Alkali-Silica Reaction and Delayed Ettringite Formation (2012). | |||
Giannini, E., Evaluation of Concrete Structures Affected by | |||
NER-031 Said Bolourchi Curriculum Vitae. | NER-031 Said Bolourchi Curriculum Vitae. | ||
NER-032 Glenn Bell Curriculum Vitae. | NER-032 Glenn Bell Curriculum Vitae. | ||
NER-033 Matthew Sherman Curriculum Vitae. | NER-033 Matthew Sherman Curriculum Vitae. | ||
ASCE Standard ASCE/SEI 7-16, Minimum Design Loads and | NER-034 ASCE Standard ASCE/SEI 7-16, Minimum Design Loads and Associated Criteria for Buildings and Other Structures (2016) [Cover & | ||
Page 1]. | Page 1]. | ||
U.S. Department of Commerce, National Bureau of Standards, NBS | NER-035 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). | ||
ASCE Standard ASCE/SEI 4-16, Seismic Analysis of Safety-Related | NER-036 ASCE Standard ASCE/SEI 4-16, Seismic Analysis of Safety-Related Nuclear Structures (2016) [Cover & Pages 9-11, 23]. | ||
Esposito, R., and Hendriks, M.A.N., Literature Review of Modelling | NER-037 Esposito, R., and Hendriks, M.A.N., Literature Review of Modelling Approaches for ASR in Concrete: A New Perspective, EUROPEAN JOURNAL OF ENVTL. & CIVIL ENGG (2017). | ||
Gocevski, V., Pathologies/Degradation Mechanisms Experienced by | NER-038 Gocevski, V., Pathologies/Degradation Mechanisms Experienced by Hydro-Quebec During the Evaluation of Gentilly-2 NPP, Report Submitted to ASCET, (June 2015). | ||
Neville, A.M., Properties of Concrete, 5th Edition, Pearson Education | NER-039 Neville, A.M., Properties of Concrete, 5th Edition, Pearson Education Limited; Harlow, Essex, England, 2012 [Cover Pages & | ||
Pages 426-27, 436-37, 444-45]. | Pages 426-27, 436-37, 444-45]. | ||
J.J. Brooks, Accuracy of Estimating Long-Term Strains in Concrete, 36 | NER-040 J.J. Brooks, Accuracy of Estimating Long-Term Strains in Concrete, 36 Magazine of Concrete Research 127, 131-45 (June 1984). | ||
Mijnsbergen, J. and Reinhardt, H. W., Long-Time Creep and Expansion Behavior of Concrete in a Marine Environment, 109 | NER-041 Mijnsbergen, J. and Reinhardt, H. W., Long-Time Creep and Expansion Behavior of Concrete in a Marine Environment, 109 American Concrete Institute Special Publication 599-624 (SP 109-27) | ||
(1994). | (1994). | ||
G.E. Troxell, et al., Long-Time Creep and Shrinkage Tests of Plain | NER-042 G.E. Troxell, et al., Long-Time Creep and Shrinkage Tests of Plain and Reinforced Concrete, 1958 Proceeding of the American Society for Testing and Materials 1101-20. | ||
NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Chapter 3 - Design of | NER-043 NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Chapter 3 - Design of Structures and Components, Equipment, and Systems § 3.7.2, Rev. | ||
4 (Sept. 2013). | 4 (Sept. 2013). | ||
Seabrook Station Unit 1, Updated Final Safety Analysis Report (UFSAR) | NER-044 Seabrook Station Unit 1, Updated Final Safety Analysis Report (UFSAR) | ||
(Rev. 19) [§ 2.5.2.5 only]. | |||
NER-045 MPR-4286, Rev. 0, Supplemental Commercial Grade Dedication | NER-045 MPR-4286, Rev. 0, Supplemental Commercial Grade Dedication Report for Seabrook ASR Test Programs (Mar. 2016) (FP101003) | ||
Report for Seabrook ASR Test Programs (Mar. 2016) (FP101003) | |||
(proprietary). | (proprietary). | ||
Seabrook Mechanical Maintenance Procedure MS0517.51, Installation | NER-046 Seabrook Mechanical Maintenance Procedure MS0517.51, Installation of Geokon Snap-Ring Borehole Extensometers, Rev. 0 (Feb. 2016) | ||
[Cover & Pages 13-19]. | [Cover & Pages 13-19]. | ||
N. Ezell et al., Experimental Collaboration for Thick Concrete | NER-047 N. Ezell et al., Experimental Collaboration for Thick Concrete Structures with Alkali-Silica Reaction (2018). | ||
L. Phan, Structural Performance of NPP Concrete Structures Affected | NER-048 L. Phan, Structural Performance of NPP Concrete Structures Affected by Alkali-Silica Reaction (ASR), Slides for NRC Regulatory Information Conference Session TH27 (2018). | ||
Intervenor C-10 Exhibits Exhibit Number | Intervenor C-10 Exhibits Exhibit Number Title INT-001-R Pre-filed Testimony of Victor E. Saouma, Ph.D. Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant - CORRECTED JUNE 20, 2019 (proprietary). | ||
Summary of Testimony of Victor E. Saouma, Ph.D. Regarding Scientific Evaluation of NextEra's Aging Management Program for Alkali-Silica | INT-002 Summary of 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 (Non-Proprietary Version). | ||
INT-003 | INT-003 Curriculum Vitae, Dr. Victor E. Saouma. | ||
Grant Award, Experimental and Numerical Investigation of Alkali Silica | INT-004 Grant Award, Experimental and Numerical Investigation of Alkali Silica Reaction in Nuclear Reactors (2014). | ||
Final (Public) Summary Report, Experimental and Numerical | INT-005 Final (Public) Summary Report, Experimental and Numerical Investigation of Alkali Silica Reaction in Nuclear Reactors, Grant No.: | ||
NRC-HQ-60-14-G-0010 (Oct. 2014 - Dec. 2017). | NRC-HQ-60-14-G-0010 (Oct. 2014 - Dec. 2017). | ||
INT-006 | INT-006 Declaration of Dr. Victor E. Saouma, Ph.D. (Feb. 12, 2019). | ||
Saouma, Review of Selected Documents Pertaining to the Structural | INT-007 Saouma, Review of Selected Documents Pertaining to the Structural Evaluation of Seabrook Nuclear Power Plant (Feb. 12, 2019) | ||
(proprietary). | (proprietary). | ||
Summary: Review of Selected Documents Pertaining to the Structural | INT-008-R Summary: Review of Selected Documents Pertaining to the Structural Evaluation of Seabrook Nuclear Power Plant (Feb. 12, 2019). | ||
INT-009 | INT-009 Reply Declaration of Victor E. Saouma, Ph.D. (March 1, 2019). | ||
Seabrook, License Amendment Request 16 Revise Current | INT-010 Seabrook, License Amendment Request 16 Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction (August 1, 2016). | ||
INT-011 NextEra Energys Evaluation of the Proposed Change Including Markup of UFSAR Pages (Proprietary) (Enclosure 1 to Letter SBK-L-16071). | |||
Category I Structures with Concrete Affected by Alkali- Silica Reaction (August 1, 2016). | INT-012 MPR-4288, Rev. 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations (July 2016) (Non-proprietary version) | ||
NextEra Energys Evaluation of the Proposed Change Including | |||
MPR-4288, Rev. 0, Seabrook Station: Impact of Alkali-Silica Reaction on | |||
(Enclosure 2 to Letter SBK-L-16071). | (Enclosure 2 to Letter SBK-L-16071). | ||
SG&H Report 160268-R-01, Rev. 0, Development of ASR Load Factors | INT-013 SG&H Report 160268-R-01, Rev. 0, Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station, Seabrook, NH (July 2016) (Enclosure 4 to Letter SBK-L-16071). | ||
MPR-4288, Rev. 0, Seabrook Station: Impact of Alkali-Silica | INT-014 MPR-4288, Rev. 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations (July 2016) (Enclosure 2 to Letter SBK-L-16071) (Proprietary). | ||
Simpson Gumpertz & Heger, Inc., "Evaluation and Design Confirmation of As-Deformed CEB, 150252-CA-02," Revision 0, July 2016 (Seabrook | INT-015 Simpson Gumpertz & Heger, Inc., "Evaluation and Design Confirmation of As-Deformed CEB, 150252-CA-02," Revision 0, July 2016 (Seabrook FP#100985) Enclosure 2 to Letter SBK-L-16153, re: Seabrook Station (Sept. 30, 2016). | ||
Revised Seabrook Station License Renewal Application Updated Final Safety Analysis Report Sections A.2.1.31 for Structures Monitoring, | INT-016 Revised Seabrook Station License Renewal Application Updated Final Safety Analysis Report Sections A.2.1.31 for Structures Monitoring, A.2.1.31A for Alkali-Silica Reaction and A.2.1.3b for Building Deformation (Enclosure 1 to Letter SBK-L-18072 re: Seabrook Station Revised Structures Monitoring Aging Management Program (May 18, 2018). | ||
Revised Seabrook Station License Renewal Application Appendix B Sections B.2.1.31 for Structures Monitoring, B.2.1.31A for Alkali-Silica | INT-017 Revised Seabrook Station License Renewal Application Appendix B Sections B.2.1.31 for Structures Monitoring, B.2.1.31A for Alkali-Silica Reaction and B.2.1.3b for Building Deformation (Enclosure 2 to Letter SBK-18072). | ||
MPR-4153, Revision 3, Seabrook Station-Approach for Determining | INT-018-R MPR-4153, Revision 3, Seabrook Station-Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction (Sept. 2017) | ||
(Non-proprietary version) (Enclosure 4 to Letter SBK-18072). | (Non-proprietary version) (Enclosure 4 to Letter SBK-18072). | ||
MPR-4273, Rev. 1, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica | INT-019-R MPR-4273, Rev. 1, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016) (Non-proprietary version) (Enclosure 5 to Letter SBK-18072). | ||
MPR-4153, Revision 3, Seabrook Station-Approach for Determining | INT-020 MPR-4153, Revision 3, Seabrook Station-Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction (Sept. | ||
2017) (Proprietary version) (Enclosure 6 to Letter SBK-18072). | 2017) (Proprietary version) (Enclosure 6 to Letter SBK-18072). | ||
MPR-4273, Rev. 1, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali- | INT-021 MPR-4273, Rev. 1, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (March 2018) (Proprietary version) (Enclosure 7 to Letter SBK-18072). | ||
Simpson Gumpertz & Heger Document No. 170444-MD-01, Rev. 1, | INT-022 Simpson Gumpertz & Heger Document No. 170444-MD-01, Rev. 1, "Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction," for Seabrook Station (Enclosure 3 to Letter SBK-L-18074, re: Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 1603) (June 7, 2018). | ||
INT-023 Simpson Gumpertz & Heger Document No. 170444-L-003 Rev. 1, Response to RAI-D8-Attachment 1 Example Calculation of Rebar Stress For a Section Subjected to Combined Effect of External Axial Moment and Internal ASR (Enclosure 4 to Letter SBK-L-18074). | |||
Concrete Affected by Alkali-Silica Reaction," for Seabrook Station (Enclosure 3 to Letter SBK-L-18074, re: Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 1603) (June 7, 2018). | INT-024 NRC Safety Evaluation Related to Amendment No. 159 to Facility Operating License No. NPF-86 (March 11, 2019). | ||
Simpson Gumpertz & Heger Document No. 170444-L-003 Rev. 1, Response to RAI-D8-Attachment 1 Example Calculation of Rebar Stress | INT-025 NRC Safety Evaluation Related to Amendment No. 159 to Facility Operating License No. NPF-86 (March 11, 2019) (proprietary). | ||
NRC Safety Evaluation Related to Amendment No. 159 to Facility | |||
NRC Safety Evaluation Related to Amendment No. 159 to Facility | |||
INT-026 Bayrak, Structural Assessment of Seabrook (Apr. 23, 2012). | INT-026 Bayrak, Structural Assessment of Seabrook (Apr. 23, 2012). | ||
Pre-filed Opening Testimony of Victor E. Saouma, Ph.D. Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali- | INT-027 Pre-filed Opening Testimony of Victor E. Saouma, Ph.D. Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant. | ||
REDACTED VERSION FILED JUNE 26, 2019. | REDACTED VERSION FILED JUNE 26, 2019. | ||
Rebuttal Testimony of Victor E. Saouma, Ph. D Regarding Scientific | INT-028 Rebuttal Testimony of Victor E. Saouma, Ph. D Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant (Proprietary). | ||
Summary of Testimony of Victor E. Saouma, Ph. D Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica | INT-029 Summary of Testimony of Victor E. Saouma, Ph. D Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant (Non-Proprietary Version). | ||
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of | UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of | ||
) | |||
NEXTERA ENERGY SEABROOK, LLC | ) | ||
NEXTERA ENERGY SEABROOK, LLC | |||
(License Amendment) | ) | ||
Docket No. 50-443-LA-2 (Seabrook Station, Unit 1) | |||
) | |||
) | |||
(License Amendment) | |||
) | |||
CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing MEMORANDUM (Regarding Pre-filed Exhibits) have been served upon the following persons by Electronic Information Exchange. | CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing MEMORANDUM (Regarding Pre-filed Exhibits) have been served upon the following persons by Electronic Information Exchange. | ||
U.S. Nuclear Regulatory Commission Office of Commission Appellate Adjudication Mail Stop: O-16B33 Washington, DC 20555-0001 ocaamail@nrc.gov U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Board Panel Mail Stop: T-3F23 Washington, DC 20555-0001 Ronald M. Spritzer, Chair Administrative Judge ronald.spritzer@nrc.gov Nicholas G. Trikouros Administrative Judge nicholas.trikouros@nrc.gov Dr. Sekazi K. Mtingwa Administrative Judge sekazi.mtingwa@nrc.gov Taylor Mayhall, Law Clerk Taylor.Mayhall@nrc.gov Joseph McManus, Law Clerk joseph.mcmanus@nrc.gov Molly Mattison, Law Clerk Molly.Mattison@nrc.gov U.S. Nuclear Regulatory Commission Office of the Secretary of the Commission Mail Stop: O-16B33 Washington, DC 20555-0001 Hearing Docket hearingdocket@nrc.gov U.S. Nuclear Regulatory Commission Office of the General Counsel Mail Stop: O-14A44 Washington, DC 20555-0001 Anita Ghosh, Esq. | |||
anita.ghosh@nrc.gov Jeremy Wachutka, Esq. | |||
jeremy.wachutka@nrc.gov | jeremy.wachutka@nrc.gov David E. Roth, Esq. | ||
david.roth@nrc.gov Jennifer E. Scro, Esq. | |||
Jennifer.Scro@nrc.gov | Jennifer.Scro@nrc.gov OGC Mail Center: Members of this office have received a copy of this filing by EIE service. | ||
NEXTERA ENERGY SEABROOK, LLC (Seabrook Station Unit 1) - Docket No. 50-443-LA-2 MEMORANDUM (Regarding Pre-filed Exhibits) | NEXTERA ENERGY SEABROOK, LLC (Seabrook Station Unit 1) - Docket No. 50-443-LA-2 MEMORANDUM (Regarding Pre-filed Exhibits) 2 NextEra Energy Seabrook, LLC 801 Pennsylvania Avenue, N.W., #220 Washington, DC 20004 Steven C. Hamrick, Esq. | ||
NextEra Energy Seabrook, LLC | steven.hamrick@fpl.com NextEra Energy Seabrook, LLC Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue NW Washington, DC 20004 Paul M. Bessette, Esq. | ||
Paul M. Bessette, Esq. | paul.bessette@morganlewis.com Ryan K. Lighty, Esq. | ||
ryan.lighty@morganlewis.com Grant Eskelsen, Esq. | ryan.lighty@morganlewis.com Grant Eskelsen, Esq. | ||
grant.eskelsen@morganlewis.com | grant.eskelsen@morganlewis.com C-10 Research & Education Foundation 44 Merrimac Street Newburyport, Mass. 01950 Natalie Hildt Treat natalie@c-10.org Harmon, Curran, Spielberg, & Eisenberg, LLP 1725 DeSales Street, NW, Suite 500 Washington, DC 20036 Diane Curran, Esq. | ||
[Original signed by Clara Sola | dcurran@harmoncurran.com | ||
Office of the Secretary of the Commission Dated at Rockville, Maryland, this 27th day of August 2019 | [Original signed by Clara Sola ] | ||
Office of the Secretary of the Commission Dated at Rockville, Maryland, this 27th day of August 2019}} | |||
Latest revision as of 14:48, 4 January 2025
| ML19239A227 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 08/27/2019 |
| From: | Ronald Spritzer Atomic Safety and Licensing Board Panel |
| To: | |
| SECY RAS | |
| References | |
| 50-443-LA-2, ASLBP 17-953-02-LA-BD01, RAS 55210 | |
| Download: ML19239A227 (17) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges:
Ronald M. Spritzer, Chairman Nicholas G. Trikouros Dr. Sekazi K. Mtingwa In the Matter of NEXTERA ENERGY SEABROOK, LLC (Seabrook Station, Unit 1)
Docket No. 50-443-LA-2 ASLBP No. 17-953-02-LA-BD01 August 27, 2019 MEMORANDUM (Regarding Pre-filed Exhibits)
On August 12, 2019, the Board issued an order to schedule a prehearing teleconference with all the parties to discuss logistics for the evidentiary hearing planned for September 24-27, 2019. The order contained a list of discussion topics and stated that the Board would prepare a final exhibit list identifying all pre-filed testimony and other exhibits (including revised exhibits) that have been filed by the participants.1 During the prehearing teleconference on August 26, 2019, the Board again stated that it would prepare a final exhibit list. This list is now attached as Appendix A.
The Board also notes that numerous prefiled exhibits contain references to documents that have not been filed in the evidentiary record. If any party desires the documentary material, website material, or incorporated reports cited in these pre-filed exhibits to be considered part of the evidentiary record, the party should promptly provide a PDF evidentiary exhibit of each item, 1 Order (Scheduling Prehearing Teleconference) at 3 (Aug. 12, 2019) (unpublished).
or the relevant portions thereof, with an appropriate exhibit cover sheet and an updated exhibit list.
FOR THE ATOMIC SAFETY AND LICENSING BOARD Ronald M. Spritzer, Chairman ADMINISTRATIVE JUDGE Rockville, Maryland August 27, 2019
/RA/
APPENDIX A: LIST OF PREFILED EXHIBITS IN THE MATTER OF NEXTERA ENERGY SEABROOK, LLC, (SEABROOK STATION, UNIT 1)
DOCKET NO. 50-443-LA-22 NRC Staff Exhibits Exhibit Number Title NRC-001 Staff Testimony.
NRC-002 Statement of Professional Qualifications of Angela Buford.
NRC-003 Statement of Professional Qualifications of Bryce Lehman.
NRC-004 Statement of Professional Qualifications of George Thomas.
NRC-005 Jacob Philip Testimony.
NRC-006 Statement of Professional Qualifications of Jacob Philip.
NRC-007 Seabrook Station Updated Final Safety Analysis Report (UFSAR),
Chapter 3, "Design of Structures, Components, Equipment and Systems, Revision 18 (October 2017).
NRC-008 to Original LAR, MPR-4273, Revision 0, Seabrook Station -
Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016).
NRC-009 to Original LAR, MPR-4273, Revision 0, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016)
(proprietary).
NRC-010 Letter from Ralph A. Dodds III, NextEra, to NRC Document Control Desk, Seabrook Station, Supplement to License Amendment Request 16-03, Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction (Sept. 30, 2016).
NRC-011 to Sept. 2016 LAR Supplement, MPR-4153, Revision 2, Seabrook Station - Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction (July 2016).
2 Exhibits containing proprietary information are so identified and highlighted in bold.
NRC-012 to Sept. 2016 LAR Supplement, Revision 2, MPR-4153, Rev. 2, Seabrook Station - Approach for Determining Through Thickness Expansion from Alkali-Silica Reaction (July 2016)
(proprietary).
NRC-013 Letter from Eric McCartney, NextEra, to NRC Document Control Desk, Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (Oct. 3, 2017).
NRC-014 Letter from Eric McCartney, NextEra, to NRC Document Control Desk, Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (Dec. 11, 2017).
NRC-015 Letter from Christopher Domingos, NextEra, to NRC Document Control Desk, Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 16-03 (June 7, 2018).
NRC-016 Letter from Eric McCartney, NextEra, to NRC Document Control Desk, Seabrook Station Revised Structures Monitoring Aging Management Program (May 18, 2018).
NRC-017 Letter from Tam Tran, NRC, to Dean Curtland, NextEra, Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal (TAC No.
ME4028) (Dec. 17, 2015).
NRC-018 Seabrook ASR-Monitoring Program Audit Report, Enclosure to Dec. 17, 2015 Letter to NextEra (undated).
NRC-019 Confirmatory Action Letter, Seabrook Station, Unit 1 - Information Related to Concrete Degradation Issues (May 16, 2012).
NRC-020 Letter from Richard A. Plasse, NRC, to Paul Freeman, NextEra, Audit Report Regarding the Seabrook Station License Renewal Application (TAC Number ME4028) (Mar. 21, 2011).
NRC-021 Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2011002 (May 12, 2011).
NRC-022 Letter from Richard J. Conte, NRC, to Paul Freeman, NextEra, NextEra Energy Seabrook - NRC License Renewal Inspection Report 05000443/2011007 (May 23, 2011).
NRC-023 Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2011003 (Aug. 12, 2011).
NRC-024 Letter from Christopher G. Miller, NRC, to Paul Freeman, NextEra, Seabrook Station - NRC Inspection Report 05000443/2011010 Related to Alkali-Silica Reaction Issue In Safety Related Structures (Mar. 26, 2012).
NRC-025 Letter from Christopher G. Miller, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - Confirmatory Action Letter Follow-up Inspection - NRC Inspection Report 05000443/2012009, Enclosure, Inspection Report No. 0500044312012009 (Dec. 3, 2012).
NRC-026 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 (Aug. 9, 2013).
NRC-027 Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2013005 (Jan. 30, 2014).
NRC-028 Letter from Glenn T. Dentel, NRC, to Kevin Walsh, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014002 (May 6, 2014).
NRC-029 Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014003 (Aug. 5, 2014).
NRC-030 Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014005, (Feb. 6, 2015).
NRC-031 Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2015002, (Aug. 5, 2015).
NRC-032 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, 2016).
NRC-033 Letter from Mel Gray, NRC, to Dean Curtland, NextEra, Seabrook Station, Seabrook Station - Inspection Report 05000443/2016008 Related to Alkali-Silica Reaction Affects On Safety-Related Concrete Structures And Notice Of Violation, (May 6, 2016).
NRC-034 Letter from to Eric McCartney, NextEra, Seabrook Station, Unit No. 1 -
Integrated Inspection Report 05000443/2016002, (Aug. 5, 2016).
NRC-035 Letter from Fred L. Bower, III, NRC, to Eric McCartney, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2016004, (Feb. 8, 2017).
NRC-036 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).
NRC-037 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).
NRC-038 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).
NRC-039 Letter from Mel Gray, III, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018011, (Aug. 10, 2018).
NRC-040 Letter from Fred L. Bower, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Integrated Inspection Report 05000443/2018003, (Nov. 13, 2018).
NRC-041 Letter from Richard Plasse, NRC, to Kevin Walsh, NextEra, Aging Management Program Audit Report Regarding the Seabrook Station License Renewal Application (TAC No. ME4028) (Dec. 23, 2013).
NRC-042 Letter from Tam Tran, NRC, to Eric McCartney, NextEra, Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal (CAC No.
ME4028) (Dec. 21, 2016).
NRC-043 Letter from Justin C. Poole, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali-Silica Reaction License Amendment Request and License Renewal Alkali-Silica Reaction Aging Management Program Review (CAC No. MF8260; EPID L-2016-LLA-0007) (July 26, 2017).
NRC-044 Letter from Justin C. Poole, NRC, to Mano Nazar, NextEra, Seabrook Station, Unit No. 1 - Site Visit Report Regarding Regulatory Audit for License Amendment Request Re: Alkali-Silica Reaction License Amendment Request and License Renewal Alkali-Silica Reaction Aging Management Program Review (CAC No. MF8260; EPID L-2016-LLA-0007) (May 21, 2018).
NRC-045 Memorandum from Eric J. Leeds, NRR, and William M. Dean, Region 1, Seabrook Alkali-Silica Reaction Issue Technical Team Charter (July 9, 2012).
NRC-046 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) (Oct. 13, 2017).
NRC-047 Memorandum from James G. Danna, NRC, to Andrea D. Veil, NRC ACRS, Seabrook Station, Unit No. 1 - Submission of Alkali-Silica Reaction License Amendment Request Draft Safety Evaluation to Support the Advisory Committee on Reactor Safeguards Review of Seabrook License Renewal (CAC No. MF8260; EPID L-2016-LLA-0007)
(Sept. 28, 2018).
NRC-048 Letter from Michael Corradini, Chairman, ACRS, to Kristine L. Svinicki, Chairman, NRC, Seabrook Station Unit 1 License Renewal Application:
Review of Licensee Program Addressing Alkali-Silica Reaction (Dec. 14, 2018).
NRC-049 American Concrete Institute (ACI) Standard 318-71, Building Code Requirements for Reinforced Concrete (1971).
NRC-050 Section Ill, Division 2, of the 1975 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for containment.
NRC-051 Report of ACI-ASCE (American Society of Civil Engineers) Committee 326, Shear and Diagonal Tension (1962).
NRC-052 ACI 408R-03, Bond and Development of Straight Reinforcing Bars in Tension (effective Sept. 24, 2003) (reapproved 2012).
NRC-053 Letter from Public Service Company of New Hampshire to NRC Region I, Office of Inspection and Enforcement re: Response to NRC IE Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts, Revision 2, November 8, 1979 (Jan 3. 1980).
NRC-054 NUREG/CR-5563, A Technical Basis for Revision to Anchorage Criteria, March 1999.
NRC-055 ACI 349-13, Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary 2013.
NRC-056 Madhu M. Karthik, et. al., Experimental Behavior of Large Reinforced Concrete Specimen with Heavy ASR and DEF [delayed ettringite formation] Deterioration, J. Struct. Eng. (2018) (published online May 31, 2018).
NRC-057 M. Kathleen Eck Olave, et. al., Performance of RC Columns Affected by ASR. II: Experiments and Assessment, Vol. 20. ASCE J. of Bridge Engg (March 2015) (published online June 12, 2014).
NRC-058 F. Habibi, et. al., Alkali Aggregate Reaction in Nuclear Concrete Structures: Part 3: Structural Shear Wall Elements, Transactions, 23rd Conference on Structural Mechanics in Reactor Technology (SMiRT-23),
Manchester, UK, August 10-14, 2015, Division I, Paper ID 044.
NRC-059 ACI 349.3R, Evaluation of Existing Nuclear Safety-Related Concrete Structures (2002) (Reapproved 2010).
NRC-060 NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011).
NRC-061 Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants (Final Report), NUREG-2192 (July 2017).
NRC-062 Interagency Agreement between NRC and NIST (Mar. 31, 2014).
NRC-063 Grant and Cooperative Agreement between NRC and Northwestern University (Sept. 30, 2014).
NRC-064 Sherry Berhoft, EPRI Senior Program Manager, NRC Commissioner Briefing on the Status of Subsequent License Renewal Preparations, EPRI Long Term Operations: Research & Development for Aging Management (Apr. 26, 2017).
NRC-065 Emma L. Wong & Sherry Bernhoft, Overview of the Electric Power Research Institutes Research for Long Term Operations, 117 Transactions of the Am. Nuclear Socy, 648, 648 (Oct. 29-Nov. 2, 2017).
NRC-066 U.S. Department of Energy, Light Water Reactor Sustainability Program A Summary of Collaborative Research and Development Activities, INL/EXT-19-52416, Rev. 0 (Jan. 2019).
NRC-067 Organisation for Economic Cooperation and Development, Nuclear Energy Agency, Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies NEA/CSNI/R(2016)13 (July 2017).
NRC-068 Organisation for Economic Cooperation and Development, Nuclear Energy Agency, Phase II of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report NEA/CSNI/R(2018)4 (Jan.
21, 2019).
NRC-069 IRSN, ODOBA Research programs, (last update Aug. 2018),
NRC-070 Research Activities FY 2018-2020, NUREG-1925, Rev. 4 (Mar. 2018).
NRC-071 NUREG/CR-7153, Expanded Materials Degradation Assessment (EMDA), Volume 4: Aging of Concrete and Civil Structures (Oct. 2014).
NRC-072 R. Park and T. Paulay, Reinforced Concrete Structures (John Wiley &
Sons, Inc. 1975).
NRC-073 David Darwin, Charles W. Dolan, and Arthur H. Nilson, Design of Concrete Structures (McGraw Hill, Inc., 15th Ed. 2016).
NRC-074 Stéphane Multon, et. al., Flexural Strength of Beams Affected by ASR, 12th International Conference on Alkali-Aggregate Reaction, Beijing, China (2004).
NRC-075 Dean J., Deschenes, et. al., ASR/DEF-Damaged Bent Caps: Shear Tests and Field Implications, Technical Report No. 12-8XXIA006 summarizing work conducted for the Texas Department of Transportation at Ferguson Structural Engineering Laboratory, The University of Texas at Austin (August 2009).
NRC-076 Canadian Standards Association (CSA) A864-00, Guide to the Evaluation and Management of Concrete Structures Affected by Alkali-Aggregate Reaction (Feb. 2000) (Reaffirmed 2005).
NRC-077 Geoffrey E. Blight and Mark G. Alexander, Alkali-Aggregate Reaction and Structural Damage to Concrete - Engineering Assessment, Repair and Management, (CRC Press Taylor & Francis Group, 2011).
NRC-078 Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Response to Confirmatory Action Letter (May 24, 2012).
NRC-079 to SBK-L-12106, The Evaluation, Impact of ASR on Concrete Structures and Attachments, (May 2012) (Interim Structural Assessment).
NRC-080 Memorandum from John G. Lamb, NRC, to Meena Khanna, NRC, Forthcoming April 23, 2012 Meeting with NextEra Energy Seabrook, LLC (NextEra) Regarding Seabrook Station Concrete Degradation (Mar. 23, 2012).
NRC-081 Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Actions for Resolution of Alkali Silica Reaction (ASR) Issues (May 3, 2012).
NRC-082 Letter from Paul O. Freeman, NextEra, to NRC, Seabrook Station Supplement to Actions for Resolution of Alkali Silica Reaction (ASR)
Issues (May 10, 2012).
NRC-083 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).
NRC-084 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).
NRC-085 Letter from William M. Dean, NRC, Kevin Walsh, NextEra, Closure of Confirmatory Action Letter 1-12-002, Seabrook Station, Unit 1 (Oct. 9, 2013).
NRC-086 Letter from Darrell J. Roberts, NRC, to Kevin Walsh, NextEra, Mid-cycle Performance Review and Inspection Plan - Seabrook Station, Unit No. 1 (Report 05000443/2013006), (Sept. 3, 2013).
NRC-087 Email from Justin Poole, NRC, to Kenneth Browne, NextEra, Audit Plan Regarding Seabrook ASR License Amendment Review, (Jan. 13, 2017).
NRC-088 Regulatory Guide (RG) 1.29, Seismic Design Classification for Nuclear Power Plants (July 2016).
NRC-089 to Original LAR, NextEra Energy Seabrook's Evaluation of the Proposed Change Including Attachment 1 Markup of UFSAR Pages (proprietary).
NextEra Exhibits Exhibit Number Title NER-001 Testimony of NextEra Witnesses Michael Collins, John Simons, Christopher Bagley, Oguzhan Bayrak, and Edward Carley (MPR Testimony).
NER-002 MPR Testimony - Attachment 1 - Glossary.
NER-003 MPR Testimony - Attachment 2 - Proprietary Appendix.
NER-004 Testimony of NextEra Witnesses Said Bolourchi, Glenn Bell, and Matthew Sherman (SGH Testimony).
NER-005 NextEra Exhibit List.
NER-006 Michael Collins Biography.
NER-007 Seabrook Structures Monitoring Program Manual, Rev. 7 (proprietary).
NER-008 John Simons Curriculum Vitae.
NER-009 Chris Bagley Curriculum Vitae.
NER-010 Dr. Oguzhan Bayrak Curriculum Vitae.
NER-011 Edward Carley Resume.
NER-012 The Institution of Structural Engineers, Structural Effects of Alkali-Silica Reaction (July 1992).
NER-013 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).
NER-014 NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report, Vol. 2 (July 2017) [Cover and Section X.M1].
NER-015 MPR-3848, Rev. 0 Seabrook Station, Approach for Shear and Reinforcement Anchorage Testing of Concrete Affected by Alkali-Silica Reaction (Apr. 2013) (FP100818) (proprietary).
NER-016 Allford, M., Expansion Behavior of Reinforced Concrete Elements Due to Alkali-Silica Reaction (Aug. 2016).
NER-017 EPRI Report 3002013192, Evaluation of Laboratory Tests to Detect Up-to-Date Expansion and Remaining Expansion in Concrete Structures Affected by Alkali-Silica Reaction (Oct. 15, 2018).
NER-018 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).
NER-019 Bayrak, O., Structural Implications of ASR; State of the Art (Feb.
2, 2012) (FP100697) (proprietary).
NER-020 MPR 0326-0062-88, Rev. 2, Initial Expansion Assessment of ASR Affected Reinforced Concrete Structures at Seabrook Station (Mar. 2018) (FP101070, Rev. 1) (proprietary).
NER-021 MPR-4231, Rev. 0, Instrumentation for Measuring Expansion in Concrete Affected by Alkali-Silica Reaction (Oct. 2015) (FP100972)
(proprietary).
NER-022 MPR-4262, Shear and Reinforcement Anchorage Testing of Concrete Affected by Alkali-Silica Reaction, Vol. I, Rev. 1 (July 2016) & Vol. II, Rev. 0 (Jan. 2016) (FP100994) [Main Report & Apps. E
& G] (proprietary).
NER-023 MPR-3722, Rev. 2, Strength Testing of Anchors in Concrete Affected by Alkali-Silica Reaction (Jan. 2016) (FP100718, Rev. 1)
[Main Report & App. A] (proprietary).
NER-024 MPR-4247, Rev. 0 Commercial Grade Dedication Report for Seabrook ASR Anchor Testing (Block Series and Girder Series Phase 2) (Dec. 2015) (FP100986) [Main Report & Apps. A & B]
(proprietary).
NER-025 MPR-4259, Commercial Grade Dedication Report of Seabrook ASR Shear, Reinforcement Anchorage and Instrumentation Testing (Jan. 2016) [Main Report, App. B, & Pages D-1745, D-2615 to 16, F-9474, G-14, and G-18 to 19] (proprietary).
NER-026 MPR-3757, Rev. 4, Shear and Reinforcement Anchorage Test Specimen Technical Evaluation (May 2014) (FP100760)
(proprietary).
NER-027 Saouma, V., Benchmark Problems for AAR FEA Code Validation (Aug.
4, 2017).
NER-028 SG&H Report 110594-RPT-02, Rev. 1, Damage Rating Index and ASR Rating (Feb. 10, 2012) (FP100702).
NER-029 EPRI Report 3002013190, Modeling Concrete Structures Affected by Alkali Silica Reaction: Hydro-Quebec Approach for Hydraulic and Nuclear Power Plants (Oct. 15, 2018).
NER-030 Giannini, E., Evaluation of Concrete Structures Affected by Alkali-Silica Reaction and Delayed Ettringite Formation (2012).
NER-031 Said Bolourchi Curriculum Vitae.
NER-032 Glenn Bell Curriculum Vitae.
NER-033 Matthew Sherman Curriculum Vitae.
NER-034 ASCE Standard ASCE/SEI 7-16, Minimum Design Loads and Associated Criteria for Buildings and Other Structures (2016) [Cover &
Page 1].
NER-035 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).
NER-036 ASCE Standard ASCE/SEI 4-16, Seismic Analysis of Safety-Related Nuclear Structures (2016) [Cover & Pages 9-11, 23].
NER-037 Esposito, R., and Hendriks, M.A.N., Literature Review of Modelling Approaches for ASR in Concrete: A New Perspective, EUROPEAN JOURNAL OF ENVTL. & CIVIL ENGG (2017).
NER-038 Gocevski, V., Pathologies/Degradation Mechanisms Experienced by Hydro-Quebec During the Evaluation of Gentilly-2 NPP, Report Submitted to ASCET, (June 2015).
NER-039 Neville, A.M., Properties of Concrete, 5th Edition, Pearson Education Limited; Harlow, Essex, England, 2012 [Cover Pages &
Pages 426-27, 436-37, 444-45].
NER-040 J.J. Brooks, Accuracy of Estimating Long-Term Strains in Concrete, 36 Magazine of Concrete Research 127, 131-45 (June 1984).
NER-041 Mijnsbergen, J. and Reinhardt, H. W., Long-Time Creep and Expansion Behavior of Concrete in a Marine Environment, 109 American Concrete Institute Special Publication 599-624 (SP 109-27)
(1994).
NER-042 G.E. Troxell, et al., Long-Time Creep and Shrinkage Tests of Plain and Reinforced Concrete, 1958 Proceeding of the American Society for Testing and Materials 1101-20.
NER-043 NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Chapter 3 - Design of Structures and Components, Equipment, and Systems § 3.7.2, Rev.
4 (Sept. 2013).
NER-044 Seabrook Station Unit 1, Updated Final Safety Analysis Report (UFSAR)
(Rev. 19) [§ 2.5.2.5 only].
NER-045 MPR-4286, Rev. 0, Supplemental Commercial Grade Dedication Report for Seabrook ASR Test Programs (Mar. 2016) (FP101003)
(proprietary).
NER-046 Seabrook Mechanical Maintenance Procedure MS0517.51, Installation of Geokon Snap-Ring Borehole Extensometers, Rev. 0 (Feb. 2016)
[Cover & Pages 13-19].
NER-047 N. Ezell et al., Experimental Collaboration for Thick Concrete Structures with Alkali-Silica Reaction (2018).
NER-048 L. Phan, Structural Performance of NPP Concrete Structures Affected by Alkali-Silica Reaction (ASR), Slides for NRC Regulatory Information Conference Session TH27 (2018).
Intervenor C-10 Exhibits Exhibit Number Title INT-001-R Pre-filed Testimony of Victor E. Saouma, Ph.D. Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant - CORRECTED JUNE 20, 2019 (proprietary).
INT-002 Summary of 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 (Non-Proprietary Version).
INT-003 Curriculum Vitae, Dr. Victor E. Saouma.
INT-004 Grant Award, Experimental and Numerical Investigation of Alkali Silica Reaction in Nuclear Reactors (2014).
INT-005 Final (Public) Summary Report, Experimental and Numerical Investigation of Alkali Silica Reaction in Nuclear Reactors, Grant No.:
NRC-HQ-60-14-G-0010 (Oct. 2014 - Dec. 2017).
INT-006 Declaration of Dr. Victor E. Saouma, Ph.D. (Feb. 12, 2019).
INT-007 Saouma, Review of Selected Documents Pertaining to the Structural Evaluation of Seabrook Nuclear Power Plant (Feb. 12, 2019)
(proprietary).
INT-008-R Summary: Review of Selected Documents Pertaining to the Structural Evaluation of Seabrook Nuclear Power Plant (Feb. 12, 2019).
INT-009 Reply Declaration of Victor E. Saouma, Ph.D. (March 1, 2019).
INT-010 Seabrook, License Amendment Request 16 Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction (August 1, 2016).
INT-011 NextEra Energys Evaluation of the Proposed Change Including Markup of UFSAR Pages (Proprietary) (Enclosure 1 to Letter SBK-L-16071).
INT-012 MPR-4288, Rev. 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations (July 2016) (Non-proprietary version)
(Enclosure 2 to Letter SBK-L-16071).
INT-013 SG&H Report 160268-R-01, Rev. 0, Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station, Seabrook, NH (July 2016) (Enclosure 4 to Letter SBK-L-16071).
INT-014 MPR-4288, Rev. 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations (July 2016) (Enclosure 2 to Letter SBK-L-16071) (Proprietary).
INT-015 Simpson Gumpertz & Heger, Inc., "Evaluation and Design Confirmation of As-Deformed CEB, 150252-CA-02," Revision 0, July 2016 (Seabrook FP#100985) Enclosure 2 to Letter SBK-L-16153, re: Seabrook Station (Sept. 30, 2016).
INT-016 Revised Seabrook Station License Renewal Application Updated Final Safety Analysis Report Sections A.2.1.31 for Structures Monitoring, A.2.1.31A for Alkali-Silica Reaction and A.2.1.3b for Building Deformation (Enclosure 1 to Letter SBK-L-18072 re: Seabrook Station Revised Structures Monitoring Aging Management Program (May 18, 2018).
INT-017 Revised Seabrook Station License Renewal Application Appendix B Sections B.2.1.31 for Structures Monitoring, B.2.1.31A for Alkali-Silica Reaction and B.2.1.3b for Building Deformation (Enclosure 2 to Letter SBK-18072).
INT-018-R MPR-4153, Revision 3, Seabrook Station-Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction (Sept. 2017)
(Non-proprietary version) (Enclosure 4 to Letter SBK-18072).
INT-019-R MPR-4273, Rev. 1, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (July 2016) (Non-proprietary version) (Enclosure 5 to Letter SBK-18072).
INT-020 MPR-4153, Revision 3, Seabrook Station-Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction (Sept.
2017) (Proprietary version) (Enclosure 6 to Letter SBK-18072).
INT-021 MPR-4273, Rev. 1, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction (March 2018) (Proprietary version) (Enclosure 7 to Letter SBK-18072).
INT-022 Simpson Gumpertz & Heger Document No. 170444-MD-01, Rev. 1, "Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction," for Seabrook Station (Enclosure 3 to Letter SBK-L-18074, re: Seabrook Station, Response to Request for Additional Information Regarding License Amendment Request 1603) (June 7, 2018).
INT-023 Simpson Gumpertz & Heger Document No. 170444-L-003 Rev. 1, Response to RAI-D8-Attachment 1 Example Calculation of Rebar Stress For a Section Subjected to Combined Effect of External Axial Moment and Internal ASR (Enclosure 4 to Letter SBK-L-18074).
INT-024 NRC Safety Evaluation Related to Amendment No. 159 to Facility Operating License No. NPF-86 (March 11, 2019).
INT-025 NRC Safety Evaluation Related to Amendment No. 159 to Facility Operating License No. NPF-86 (March 11, 2019) (proprietary).
INT-026 Bayrak, Structural Assessment of Seabrook (Apr. 23, 2012).
INT-027 Pre-filed Opening Testimony of Victor E. Saouma, Ph.D. Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant.
REDACTED VERSION FILED JUNE 26, 2019.
INT-028 Rebuttal Testimony of Victor E. Saouma, Ph. D Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant (Proprietary).
INT-029 Summary of Testimony of Victor E. Saouma, Ph. D Regarding Scientific Evaluation of NextEras Aging Management Program for Alkali-Silica Reaction at the Seabrook Nuclear Power Plant (Non-Proprietary Version).
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
)
NEXTERA ENERGY SEABROOK, LLC
)
Docket No. 50-443-LA-2 (Seabrook Station, Unit 1)
)
)
(License Amendment)
)
CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing MEMORANDUM (Regarding Pre-filed Exhibits) have been served upon the following persons by Electronic Information Exchange.
U.S. Nuclear Regulatory Commission Office of Commission Appellate Adjudication Mail Stop: O-16B33 Washington, DC 20555-0001 ocaamail@nrc.gov U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Board Panel Mail Stop: T-3F23 Washington, DC 20555-0001 Ronald M. Spritzer, Chair Administrative Judge ronald.spritzer@nrc.gov Nicholas G. Trikouros Administrative Judge nicholas.trikouros@nrc.gov Dr. Sekazi K. Mtingwa Administrative Judge sekazi.mtingwa@nrc.gov Taylor Mayhall, Law Clerk Taylor.Mayhall@nrc.gov Joseph McManus, Law Clerk joseph.mcmanus@nrc.gov Molly Mattison, Law Clerk Molly.Mattison@nrc.gov U.S. Nuclear Regulatory Commission Office of the Secretary of the Commission Mail Stop: O-16B33 Washington, DC 20555-0001 Hearing Docket hearingdocket@nrc.gov U.S. Nuclear Regulatory Commission Office of the General Counsel Mail Stop: O-14A44 Washington, DC 20555-0001 Anita Ghosh, Esq.
anita.ghosh@nrc.gov Jeremy Wachutka, Esq.
jeremy.wachutka@nrc.gov David E. Roth, Esq.
david.roth@nrc.gov Jennifer E. Scro, Esq.
Jennifer.Scro@nrc.gov OGC Mail Center: Members of this office have received a copy of this filing by EIE service.
NEXTERA ENERGY SEABROOK, LLC (Seabrook Station Unit 1) - Docket No. 50-443-LA-2 MEMORANDUM (Regarding Pre-filed Exhibits) 2 NextEra Energy Seabrook, LLC 801 Pennsylvania Avenue, N.W., #220 Washington, DC 20004 Steven C. Hamrick, Esq.
steven.hamrick@fpl.com NextEra Energy Seabrook, LLC Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue NW Washington, DC 20004 Paul M. Bessette, Esq.
paul.bessette@morganlewis.com Ryan K. Lighty, Esq.
ryan.lighty@morganlewis.com Grant Eskelsen, Esq.
grant.eskelsen@morganlewis.com C-10 Research & Education Foundation 44 Merrimac Street Newburyport, Mass. 01950 Natalie Hildt Treat natalie@c-10.org Harmon, Curran, Spielberg, & Eisenberg, LLP 1725 DeSales Street, NW, Suite 500 Washington, DC 20036 Diane Curran, Esq.
dcurran@harmoncurran.com
[Original signed by Clara Sola ]
Office of the Secretary of the Commission Dated at Rockville, Maryland, this 27th day of August 2019