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Category:Report
MONTHYEARL-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio L-2023-028, And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program ML21062A1462021-04-21021 April 2021 Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Seabrook Station Unit 1 Independent Spent Fuel Storage Installation (2012 and 2015) L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds ML19002A1602019-03-12012 March 2019 Nrc'S Record of Decision for the License Renewal Application for Seabrook Station, Unit 1 - 1-4-19 ML19101A4552018-11-14014 November 2018 Samuel Miranda Public Comments for November 15, 2018 Seabrook LRA Meeting ML18012A5682018-01-12012 January 2018 Technical Evaluation Report: Storm Surge_Seabrook_January2018 SBK-L-17172, Seventh Annual Update to the License Renewal Application2017-10-18018 October 2017 Seventh Annual Update to the License Renewal Application SBK-L-17136, Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information2017-08-28028 August 2017 Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information ML17191A4122017-07-10010 July 2017 NextEra Service Position Paper: Seabrook Service Water TS 3.7.4 SBK-L-17099, Flooding Focused Evaluation for Impact of New Flooding Hazard Information2017-06-28028 June 2017 Flooding Focused Evaluation for Impact of New Flooding Hazard Information L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 ML16279A0502016-07-31031 July 2016 Enclosure 3: MPR-4153, Revision 2, Seabrook Station-Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction, July 2016 (Seabrook Fp# 100918) (Non-proprietary) ML16279A0492016-07-31031 July 2016 Enclosure 2: Simpson Gumpertz & Heger, Inc., Evaluation and Design Confirmation of As-Deformed Ceb, 150252-CA-02, Revision 0, July 2016 (Seabrook FP#100985) ML16216A2422016-07-31031 July 2016 MPR-4273, Revision 0, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction, July 2016 ML16216A2412016-07-31031 July 2016 MPR-4288, Revision 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations, July 2016 SBK-L-16071, Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 02016-07-27027 July 2016 Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 0 SBK-L-16108, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events2016-07-26026 July 2016 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events ML16147A1962016-04-29029 April 2016 10 CFR 50.59 Report, Revision 17 to Updated Final Safety Analysis Report, Revision 14 to Appendix R, Revision 15 to Appendix a, and Revision 146 to the Technical Requirements Manual ML16117A3122016-04-26026 April 2016 SBK-L-16056 - NextEra Energy Seabrook, LLC - Revised Response to NRC 12/23/2015 Questions on Ceb Root Cause ML16068A1352016-02-27027 February 2016 Attachment 3 - Clean Copy of Seabrook Emergency Action Levels - Initiating Conditions, Threshold Values and Basis ML16068A1392016-02-27027 February 2016 Attachment 5 - Technical Information for Proposed Initiating Conditions and Emergency Action Levels ML16068A1312016-02-27027 February 2016 Attachment 2 - Markup of Seabrook Station Emergency Action Levels -Initiating Conditions, Threshold Values and Basis ML16068A1372016-02-27027 February 2016 Attachment 4 - NEI 99-01, Rev. 6, Deviations and Differences, Seabrook Station Nuclear Power Plant - Unit 1 SBK-L-15195, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report2015-11-0707 November 2015 Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report ML15274A2142015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-1 Through Figure 4-33 SBK-L-15181, FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End2015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End ML15274A2122015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Pp. 1 Through Figure 2-1 ML15208A0492015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights SBK-L-14229, Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...2014-12-19019 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The... ML14216A4062014-07-24024 July 2014 Attachment 5, WCAP-17444-NP, Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Seabrook Unit 1, (Non-proprietary) ML14216A4052014-07-24024 July 2014 Attachment 3, WCAP-17441-NP, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation SBK-L-14090, ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report.2014-05-31031 May 2014 ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report. ML14030A5522014-02-25025 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14049A1972014-02-14014 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Seabrook Station, TAC No.: MF0836 ML13295A2522013-12-17017 December 2013 Review of the 2012 Steam Generator Tube Inspections ML13267A3882013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13260A1612013-07-31031 July 2013 ANP-3243NP, Rev. 0, Seabrook Station Unit I Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report ML13189A1972013-07-0202 July 2013 Third Annual Update to License Renewal Application ML13099A0192013-03-19019 March 2013 Attachment 5 to SBK-L-13061, Holtec Non-Proprietary Licensing Report HI-2114996, Rev. 3, Licensing Report for Seabrook Spent Fuel Pool and New Fuel Vault Analyses. ML12340A4872012-11-21021 November 2012 Enclosure to SBK-L-12242, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML12339A2742012-09-13013 September 2012 Concrete Summary 4-12 SBK-L-12101, NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring2012-05-16016 May 2012 NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring ML12179A2822012-03-15015 March 2012 ASR at Seabrook Station, Shear and Lap Splice Testing ML12038A0382012-01-30030 January 2012 Licensing Report for Seabrook Spent Fuel Pool and New Fuel Vault Analyses (Holtec International Document HI-2114996, Revision 2 SBK-L-12256, WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation2011-10-31031 October 2011 WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation 2024-05-30
[Table view] Category:Miscellaneous
MONTHYEARL-2023-028, And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 And Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML19002A1602019-03-12012 March 2019 Nrc'S Record of Decision for the License Renewal Application for Seabrook Station, Unit 1 - 1-4-19 ML19101A4552018-11-14014 November 2018 Samuel Miranda Public Comments for November 15, 2018 Seabrook LRA Meeting SBK-L-17172, Seventh Annual Update to the License Renewal Application2017-10-18018 October 2017 Seventh Annual Update to the License Renewal Application ML17191A4122017-07-10010 July 2017 NextEra Service Position Paper: Seabrook Service Water TS 3.7.4 SBK-L-17099, Flooding Focused Evaluation for Impact of New Flooding Hazard Information2017-06-28028 June 2017 Flooding Focused Evaluation for Impact of New Flooding Hazard Information SBK-L-16108, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events2016-07-26026 July 2016 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events ML16147A1962016-04-29029 April 2016 10 CFR 50.59 Report, Revision 17 to Updated Final Safety Analysis Report, Revision 14 to Appendix R, Revision 15 to Appendix a, and Revision 146 to the Technical Requirements Manual ML16117A3122016-04-26026 April 2016 SBK-L-16056 - NextEra Energy Seabrook, LLC - Revised Response to NRC 12/23/2015 Questions on Ceb Root Cause SBK-L-15195, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report2015-11-0707 November 2015 Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report ML15274A2142015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-1 Through Figure 4-33 ML15274A2122015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Pp. 1 Through Figure 2-1 SBK-L-15181, FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End2015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End ML15208A0492015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights SBK-L-14229, Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...2014-12-19019 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The... SBK-L-14090, ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report.2014-05-31031 May 2014 ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report. ML13295A2522013-12-17017 December 2013 Review of the 2012 Steam Generator Tube Inspections ML13267A3882013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13189A1972013-07-0202 July 2013 Third Annual Update to License Renewal Application SBK-L-12101, NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring2012-05-16016 May 2012 NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring ML12179A2822012-03-15015 March 2012 ASR at Seabrook Station, Shear and Lap Splice Testing SBK-L-11173, First Annual Update to License Renewal Application and Changes to LRA Appendix a2011-08-25025 August 2011 First Annual Update to License Renewal Application and Changes to LRA Appendix a SBK-L-10118, 10 CFR 72.48 Report of Changes, Tests and Experiments2010-08-10010 August 2010 10 CFR 72.48 Report of Changes, Tests and Experiments ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1036203182010-01-21021 January 2010 Attachment 2, Document SEA-FLU-001-R-004, Rev 0, Non-Proprietary Version of Seabrook Station Reactor Pressure Vessel Fluence Evaluation at 55 EFPY ML0926503702009-08-12012 August 2009 Westinghouse Electric Company LLC, LTR-SGMP-09-100 NP-Attachment, Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators, Attachment 7 ML0926802512009-04-30030 April 2009 Attachment 3, Corrected Pages for WCAP-17071-NP, Revision 0 (Non-Proprietary) SBK-L-08179, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2008-10-14014 October 2008 Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. SBK-L-06227, Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document2007-10-17017 October 2007 Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document SBK-L-07040, Semi-Annual Fitness-For-Duty Report for July-December 20062007-02-26026 February 2007 Semi-Annual Fitness-For-Duty Report for July-December 2006 SBK-L-07002, NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day Report2007-01-0404 January 2007 NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day Report ET 06-0035, Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove2006-10-0505 October 2006 Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove SBK-L-06176, Semi-Annual Fitness-For-Duty Report2006-08-31031 August 2006 Semi-Annual Fitness-For-Duty Report L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire SBK-L-06071, Reactor Vessel Weld Wire Material Data Update2006-04-12012 April 2006 Reactor Vessel Weld Wire Material Data Update SBK-L-06068, Resubmittal of Semi-Annual Fitness-For-Duty Report2006-03-24024 March 2006 Resubmittal of Semi-Annual Fitness-For-Duty Report SBK-L-06017, Semi-Annual Fitness-for-Duty Report2006-03-0101 March 2006 Semi-Annual Fitness-for-Duty Report ML0727105622005-12-16016 December 2005 Caoldon Non-Proprietary Information Package for Seabrook/Nrc Meeting on December 16, 2005 SBK-L-05166, Semi-Annual Fitness-for-Duty Report2005-08-19019 August 2005 Semi-Annual Fitness-for-Duty Report SBK-L-05122, Cycle 11 Core Operating Limits Report2005-05-26026 May 2005 Cycle 11 Core Operating Limits Report SBK-L-05030, Semi-Annual Fitness-For-Duty Report from 07/1/2004 Through 12/31/20042005-02-23023 February 2005 Semi-Annual Fitness-For-Duty Report from 07/1/2004 Through 12/31/2004 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement SBK-L-04019, Semi-Annual Fitness-For-Duty Report2004-08-26026 August 2004 Semi-Annual Fitness-For-Duty Report ML0415603482004-05-26026 May 2004 Special Report: Explosive Gas Monitoring Instrumentation Inoperable Greater than 30 Days ML0410501752004-04-0101 April 2004 Background Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate ML0404906712004-02-0909 February 2004 Semi-Annual Fitness-for-Duty Report for Period Ending December 31, 2003 ML0402105202004-01-16016 January 2004 Part 21 Report Involving an Undersized Emergency Feedwater Pump Shaft ML0336405912003-12-23023 December 2003 Unusual Fish Impingement - December 2003 ML0332904522003-11-17017 November 2003 Cycle 10 Core Operating Limits Report 2023-03-27
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Enclosure to SBK-L-12129 Seabrook Station ASR at Seabrook Station - Shear and Lap Splice Testing
Page 1 of 9 ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING MARCH 15, 2012 OGUZHAN BAYRAK, PH.D., P.E.
DIRECTOR, FSEL BAYRAK@MAIL.UTEXAS.EDU FERGUSON STRUCTURAL ENGINEERING LABORATORY THE UNIVERSITY OF TEXAS AT AUSTIN 512.471.3062 TEL 10100 BURNET ROAD, BUILDING 177 512.471.1944 FAX AUSTIN, TEXAS USA 78758
ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING TABLE OF CONTENTS 1 INT RO DUCT ION ................................................................................................................... 1 2 SCOPE OF SHEAR TEST PROGRAM ................................................................................. 1 3 SCOPE OF LAP SPLICE TEST PROGRAM ........................................................................... 2 4 RESEARCH M ETHODOLOGY ........................................................................................... 3 FERGUSON STRUCTURAL ENGINEERING LABORATORY
ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING 1 INTRODUCTION Evaluation and literature review efforts conducted to date have led MPR associates and Dr. Oguzhan Bayrak to conclude that a well-substantiated assessment of the safety-related structures is not possible without additional test data. Data currently available within the literature are generally limited and/or lack relevance to the structural details of Seabrook Station.
The test programs proposed below will provide the data and insights necessary to establish the current and future implications of ASR deterioration within the most vulnerable structural details of Seabrook Station. Specifically, the Shear Test Program (STP) and Lap Splice Test Program (LSTP) will elucidate the effects of ASR with regards to the out-of-plane shear strength of, and lap splice development within, walls without transverse reinforcement. The use of representative scale and materials will ensure that data collected during each of the test programs will be directly applicable to the assessment and management of safety-related structures at Seabrook Station.
Due to similarities in the specimen geometry and test methods, the Shear Test Program and Lap Splice Test Program will be successfully completed in parallel. Descriptions of the test programs are provided below and are followed by a discussion regarding the research methodology common to both test programs (i.e. fabricate, condition, and test).
2 SCOPE OF SHEAR TEST PROGRAM (SPT)
A total of nine (9) reinforced concrete beams will be fabricated to study the effects of ASR on the out-of-plane shear performance of walls found within the B Electrical Tunnel of Seabrook Station. The purpose of each of the nine specimens is outlined below.
" Control I Establishment of Baseline Shear Performance I One (1) Specimen: One of the nine beams will be tested to (i) obtain the baseline (undamaged) shear performance of the fully configured specimen and (ii) provide an indication of the margin that exists between the actual (experimentally-determined) strength of the structural wall and the calculated strength by using relevant provisions of ACI 318.
" Series I I Assessment of Current and Long-Term Degradation I Four (4) Specimens:
Three of the nine beams will be tested to assess the degradation of shear performance at three different levels of ASR deterioration. The first beam will be tested when the severity of the ASR deterioration is representative of the current state of the walls found within the B Electrical Tunnel. Subsequent tests will be conducted at increasing levels of deterioration. The fourth specimen will serve as a spare and testing will be contingent of the results of the other Series I specimens.
" Series II I Assessment of Wall Retrofit Techniques I Four (4) Specimens: Three of the nine beams will be tested to assess the efficacy of retrofit techniques (to be FERGUSON STRUCTURAL ENGINEERING LABORATORY I
FE ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING determined) in enhancement of the out-of-plane shear capacity. The retrofit techniques and level(s) of deterioration to be assessed within the three tests will be dependent on the results of the unmodified specimens. The fourth specimen will serve as a spare and testing will be contingent on the results of the other Series IIspecimens.
The general layout of a specimen for the Shear Test Program is shown in Figure 1. The specimen scale is equivalent to the scale of the walls found within the B Electrical Tunnel. The reinforcement pattern will be designed and detailed to: (i) represent the lack of through-thickness reinforcement within the walls of the B Electrical Tunnel and (ii) enable focused study of unreinforced shear behavior at various levels of ASR degradation.
l4 L1 Applied Load TBDI Reinforcement Mats 2 Test Region Support Reaction Support Reaction NJ
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3T-2" 21'-4" T-2" Figure 1: General Layout of Shear Test Specimen 3 SCOPE OF LAP SPLICE TEST PROGRAM (LSTP)
A total of nine (9) reinforced concrete beams will be fabricated to study the effects of ASR on the lap splice development within the walls of the B Electrical Tunnel of Seabrook Station. The purpose of each of the nine specimens is outlined below.
Control I Establishment of Baseline Lap Splice Performance I One (1) Specimen: One of the nine beams will be tested to (i) obtain the baseline (undamaged) lap splice performance of the fully configured specimen and (ii) provide an indication of the margin that exists between the actual (experimentally-determined) strength of the structural wall and the calculated strength by using relevant provisions of ACI 318.
FERGUSON STRUCTURAL ENGINEERING LABORATORY 2
ASR AT SEABROOK STATION FSEL SHEAR AND LAP SPLICE TESTING
" Series I I Assessment of Current and Long-Term Degradation I Four (4) Specimens:
Three of the nine beams will be tested to assess the degradation of lap splice performance at three different levels of ASR deterioration. The first beam will be tested when the severity of the ASR deterioration is representative of the current state of the walls found within the B Electrical Tunnel. Subsequent tests will be conducted at increasing levels of deterioration. The fourth specimen will serve as a spare and testing will be contingent of the results of the other Series I specimens.
" Series II I Assessment of Wall Retrofit Techniques I Four (4) Specimens: Three of the nine beams will be tested to assess the efficacy of retrofit techniques (to be determined) in enhancement of the lap splice performance. The retrofit techniques and level(s) of deterioration to be assessed within the three tests will be dependent on the results of the unmodified specimens. The fourth specimen will serve as a spare and testing will be contingent on the results of the other Series II specimens.
The general layout of a specimen for the Lap Splice Test Program is shown in Figure 2. The specimen geometry is equivalent to the Shear Test Program and the scale of the walls found within the B Electrical Tunnel. The reinforcement pattern will be designed and detailed to: (i) represent the lack of through-thickness reinforcement within the walls of the B Electrical Tunnel and (ii) enable focused study of lap splice behavior at various levels of ASR degradation. With regards to the second criteria, it will be necessary to provide transverse reinforcement at the specimen ends to preclude the premature shear failures and enforce lap splice failure within the constant moment region (i.e. center of the specimen).
TBD 01 Applied Loads I01 TBD Support Reaction Support Reaction I4 0lo pill 0I 21'-4" 3'-2" Figure 2: General Layout of Lap Splice Specimen FERGUSON STRUCTURAL ENGINEERING LABORATORY 3
ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING 4 RESEARCH METHODOLOGY Each test program will feature distinct reinforcement details and testing configurations, but will otherwise adhere to the same workflow: fabrication, conditioning, and structural testing.
Procedures for specimen fabrication will build upon techniques successfully implemented during ASR-related studies at Ferguson Structural Engineering Laboratory. Trial batching will be conducted to develop a concrete mixture that is well-suited to the objectives of the current program. In particular, the final concrete mixture will: (i) rapidly generate ASR damage similar to, and in excess of, that found within the walls of the B Electrical Tunnel, and (ii) result in hardened mechanical performance that is representative of the concrete placed within the B Electrical Tunnel.
All specimens, with the exception of the control beams, will be stored outside of FSEL and subjected to wetting-and-drying cycles to exacerbate/accelerate the ASR deterioration. The time-dependent severity of the ASR deterioration will be characterized by two separate methods. The severity of cracking within the cover concrete will be established through visual inspections and indexing methods. The severity of ASR-related dimensional expansions will be independently recorded by means of reference pins embedded within the. structural core of each member. Large-scale shear or lap splice testing will commence when a suitable amount of ASR deterioration has developed. The means of large-scale shear testing at Ferguson Structural Engineering Laboratory are outlined within the sections below.
4.1 LARGE-SCALE BEAM TEST FACILITY Static loading of each specimen will be conducted within the Large-Scale Beam Testing Facility. Hydraulic ram(s), supported by the strong floor of the testing facility, will exert an upward force at the desired location(s). Simple supports will be provided at the two large steel plate girders (i.e. transfer beams) and high strength threaded rods will transfer the specimen reactions to the floor. The configuration of the test frame for the Shear Test Program is illustrated in Figure 3 through Figure 5. Shear-dominated and flexure-dominated specimens have been successfully tested within the Large-Scale Beam Testing Facility, as illustrated in Figure 6 and Figure 7.
A well-defined, simply-supported testing condition will be created by the installation of roller and pin assemblies at the load(s) and support points; respectively. To permit free rotation and translation at the applied load(s), a three-inch diameter steel bar will be allowed to roll freely between a pair of four-inch thick steel plates. Rotations will be similarly released at each support through the use of two-inch diameter steel bars and two-inch thick steel plates. Axial restraint of the specimens will be limited by the lateral flexibility of the threaded rods at each support.
Each of the specimens will be monotonically loaded to failure in increments equal to approximately one-tenth of the full load-carrying capacity. Structural cracking and other forms of structural distress will be identified and noted between each of the load steps. Photographs of the test region will be used to document the propagation of cracks and the final failure mode will be documented on a video camera.
FERGUSON STRUCTURAL ENGINEERING LABORATORY 4
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2 m
I-z z 0 0 I-0 M U, 0
m)
Figure 7: Large-Scale Beam Test Facility Configured for Flexure-Dominated Testing
ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING 4.2 INSTRUMENTATION AND DATA ACQUISITION A comprehensive set of instrumentation (Figure 8) will be utilized to capture the data necessary to uniquely characterize the behavior of each specimen. Comparison of the measurements and observations made during the control and damage specimen tests will be vital to identifying the implications of ASR deterioration.
Each of the transducers described below will be wired to bridge completion modules and then interrogated via a 120-channel scanner. The voltage output will be converted into valid engineering data via predetermined calibration factors. A computer with necessary software installations will allow storage and visualization of data in real time. Layouts of the instrumentation for the shear and lap splice test programs are shown in Figure 9.
The reaction at each support will be measured by a set of four load cells. As shown in Figure 8A and Figure 9, the center-hole load cells will be individually placed over each high-strength rod. The reaction nuts and transfer nuts will be leveled prior to applying load to ensure an even distribution of the load among the rods (and corresponding force transducers).
To monitor the displacements, multiple displacement transducers will be positioned along the bottom side of each specimen. Displacements measured at the centerline, load point(s), and each support will be used to isolate the deflection of the specimen. The location of each displacement transducer is illustrated within Figure 9. Typical installation of a displacement transducer is illustrated in Figure 8B.
Figure 8: Instrumentation (A) Load Cells (B) Displacement Transducer FERGUSON STRUCTURAL ENGINEERING LABORATORY 10
ASR AT SEABROOK STATION FSEL SHEAR AND LAP SPLICE TESTING LLoad Cells Load Cells j
Test Region
_**~Displaceu ment Load Cells Load Cells Test _
Region Displacement' I Transducers I-I~
Figure 9: General Instrumentation Layout (A) Shear Test Program (B) Lap Splice Test Program FERGUSON STRUCTURAL ENGINEERING LABORATORY 11
ASR AT SEABROOK STATION SHEAR AND LAP SPLICE TESTING 4.3 POST-TEST ANALYSES: DESIGN MARGIN Within the context of the Shear Test Program, testing of a control specimen (free from ASR deterioration) will provide an indication of the margin that exists between the in-situ strength of the tunnel walls and the shear capacity calculated by application of ACI 318 Eq. 11-3 (Vc=2,/fbwd ). In reference to the control test outcome, the design margin will be inferred from a comparison of the maximum shear carried by the test region (Vtest) and the calculated shear capacity (VJ).
A comparison of this nature is justified given the similarities that exist between the proposed test program and the empirical bases of ACI 318 Eq. 11-3. More specifically, ACI 318 Eq. 11-3 was derived by ACI Committee 326 (1962) on the basis of test data collected from simply supported shear tests equivalent to the tests proposed here.
Post-test analysis will be necessary to determine the maximum shear carried by the test region, Vtest.
Figure 10 includes the free-body diagram and equations necessary to calculate the full shear force at the critical section. The critical section will be defined at the center of the test region under consideration. It should be noted that the near reaction (RA) will be taken as the sum of the load cell measurements at that support.
Support Reaction J-WLRA = (1-a) P, 4 i1 A 4_.i .. ý_ 4 4_.i ._ý. _1 7.1 ; ;7_AA.ýWDLýA 4 2
+ WD(L + LA)
(1a)14 (1-a)L aL
-r P'14 LA L Critical Section L LA aL/2 Vtest = R + WDL(LA+ aL/2)
Figure 10: Shear Force Diagram for a Typical Shear Test Similar analyses can and will be completed for tests conducted under the auspices of the Lap Splice Testing Program. It should be noted that a well-developed lap splice should enable full utilization of the FERGUSON STRUCTURAL ENGINEERING LABORATORY 12
ASR AT SEABROOK STATION FSEL SHEAR AND LAP SPLICE TESTING reinforced concrete member in flexure. In reference to the control test outcome, the design margin will be inferred from a comparison of the maximum moment carried by the member (Mtest) and the flexural capacity (M,) calculated according to the provisions of ACI 318.
4.4 POST-TEST ANALYSES: FLEXURAL STIFFNESS Analysis of the load-deflection responses of both shear and lap splice specimens, with and without deterioration, will provide an indication of ASR-related changes in flexural stiffness. As shown in Figure 11, the flexural stiffness (k) of a given member may be inferred from the linear-elastic portion of the load-deflection response. The flexural stiffness of each specimen, control and ASR-affected alike, will be determined in this manner. Comparison of the values will thereby enable a quantitative assessment of the ASR-related changes in flexural stiffness.
P k-ABEAM a-"
kASR 0.
kCONTROL Deflection, ABEAM Figure 11: Comparison of Load-Deflection Responses It should be noted that post-test analysis of the shear test data will be necessary to determine the deflection of the specimen at the load point, ABEAM. Rigid body displacement of the specimen at both supports ( 6 NEAR and 6 FAR) will be factored out of the displacement measured at the load point ( 6 LOAD) as shown in Figure 12. Response of the lap splice specimens will likely be characterized by the displacement at the centerline; similar analyses will be conducted to factor out rigid body displacement of the specimen.
FERGUSON STRUCTURAL ENGINEERING LABORATORY 13
ASR AT SEABROOK STATION FSEL SHEAR AND LAP SPLICE TESTING Support Reaction ABEAM - 8LOAD - AS "3
Support Reaction 6
NEAR 6 6 6 As = FAR+ (1-a)( NEAR- FAR) 6 = recorded displacement 8FAR{
A = calculated displacement 1
Applied Load
,I, -1 (1-a)L aL Figure 12: Calculation of Specimen Displacements and Deformations FERGUSON STRUCTURAL ENGINEERING LABORATORY 14