Similar Documents at Surry |
---|
Category:Letter
MONTHYEARML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20244032024-10-0303 October 2024 Cyber Security Inspection Report 05000280-2024403 and 05000281-2024403 Cover Letter (Public) IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 – Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML23089A3542023-03-30030 March 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21098A2612021-04-0808 April 2021 Subsequent License Renewal Application, Response to Request for Additional Information Re Environmental Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21056A5412021-02-25025 February 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response ML21042B9262021-02-11011 February 2021 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative Requests S1-I5-ISl-05 and S2-I5-ISl-06 - Response to Request for Additional Information ML22040A1012021-02-0909 February 2021 Response to Request for Additional Information 2021 Steam Generator Inservice Report ML20296A7272020-10-22022 October 2020 Stations Units 1 & 2 - Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break LOCA Supplement to the Response to Request for Additional Information ML20247J6352020-09-0303 September 2020 Virginia Electric & Power Co - Subsequent License Renewal Application (SLRA) Environmental Review, Response to Request for Additional Information Concerning Aquatic Resources ML20181A4222020-06-29029 June 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information ML20181A3082020-06-23023 June 2020 Response to Request for Additional Information on 2019 Steam Generator Inservice Inspection Report ML20269A4072020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 2 of 3 ML20269A4062020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 3 of 3 ML20269A4082020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 1 of 3 ML20149K6942020-05-28028 May 2020 Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident ML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information ML19350A0042019-12-12012 December 2019 License Amendment Request Addition of 24-Hour Completion Time for an Inoperable Reactor Trip Breaker Response to NRC Request for Additional Information ML19283B6222019-10-10010 October 2019 Subsequent License Renewal Application Safety Review - Documentation of Draft Third Round Requests for Additional Information ML19291B0342019-10-0101 October 2019 Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19269B7342019-09-19019 September 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Sets 3 and 4 Revised SLRA Mark-Ups ML19267A0422019-09-16016 September 2019 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information Set 2 ML19253B3302019-09-0303 September 2019 Response to Requests for Additional Information - Sets 3 and 4 - Subsequent License Renewal Application ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19198A0592019-07-11011 July 2019 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations 2024-05-07
[Table view] |
Text
...... . \..*'
e RICHMOND, VIRGIN .IA 23261 i **-~
Febr'.uary 8, 1978 Hr. Edson G. Case, Acting Director Serial No. 0 Office of Nuclear Reactor Regulation PO&M/HSM:wbh ATTN: Mr. Robert W. Reid, Chief Docket Nos. 50-280 Operating Reactors Branch No. 4 50-281 Division of Operating Reactors License Nos. DPR~32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20355
Dear Mr. Case:
The purpose of this letter is to submit supplemental information concerning the High Density Spent Fuel Storage Racks for Surry Power Station Unit Nos. 1 and 2. This information is being submitted as a result of dis-cussions between Vepco and members of your staff.
The applicable codes used in the design of the high density spent fuel storage racks are discussed in section 6. 3 .1.1 of the report "Summary of Proposed Modifications To The Spent Fuel Pool Associated With Increasing Storage Capacity for Surry Power Station Unit Nos. 1 and 2 11 submitted with our letter of May 27, 1977, Serial No. 186. The codes used in the design, fabrication, inspection, and installation are listed in attac-hment 1. It should be noted that it was not possible to use the ASME code for the design of the spent fuel racks because the ASME code is a pressure vessel code and does not cover spent fuel racks. However, because the ASME code could be ap-
- plied to other phases of the project besides design, it was used for the fab-rication, inspection, and installation of the spent fuel racks. The design of the spent fuel racks was done using the AISC code.
We believe that both of these codes represent quality standards of the industry and provide reasonable assurance that the racks will perform their intended function in accordance with applicable criteria, rules and re-gulations.
In our letter of September 29, 1977 a response to question 7(c) *from your letter of August 25, 1977 was provided. A more detail discussion of this question is provided as attachment 2.
As your staff is aware, we plan to refuel Unit No. 1 on or about April 1, 1978. In order to perform this refueling it is necessary that at least a por-tion of the new racks be installed. In order to assure that the racks are in-stalled by April 1, 1978 it is necessary that we commence installation by March 1, 1978. Your approval is requested so that we can proceed with installation.
78044005:2
e e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Edson.G. Case Page l'lo. 2 If you have any questions or connnents on this material, we would be pleased to meet with your staff at their convenience to cliscuss them.
Very truly yours, to. )1}7. ~tt't~a,/
C. M. Stallings Vice President - Power Supply and Production Operations Attachments cc: Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II
- ATTACHMENT 1 APPLICABLE CODES USED IN THE DESIGN FABRICATION, INSPECTION, AND INSTALLATION OF THE HIGH DENSITY SPENT FUEL STORAGE RACKS FOR SURRY POWER STATION
- 1. Design
- a. A.I.S.C. Manual -of Steel Construction, Seventh Edition, 1970.
- 2. Fabrication
- a. ASME VIII, ASME Boiler and Pressure Vessel Code,Section VIII.
- b. ASME IX, ASME Boiler and. Pressure Vessel Code,Section IX Welding and Brazing Qualifications.
- 3. Inspection
- a. ASME V, ASME Boiler and Pressure Vessel Code,Section V, Nondestruc-tive Examination.
- 4. Installation
- a. ASHE VIII, ASHE Boilerand Pressure Vessel Code,Section VIII, Appendix 9.
- b. ASME IX, ASME Boiler and Pressure Vessel Code,Section IX.
',.it-- . '\ti e
ATTACHMENT 2 Question 7(c):
Discuss the effects of a straight drop through a storage can and im-pacting on the liner. Indicate the local and overall effects of this postulated impact load.
Response
If a fuel assembly was to drop straight through a storage can it would not impact on the fuel pool liner but would impact on the bottom of the storage can. The storage cell rests on four (4)
- 1. 5" X 1. 5" legs *through which the impact loads would be transmitted to the fuel pool floorw A calculation has been performed using empirical equations and energy balance methods to .determine the effects of the free fa11 of a fuel assembly through a storage cell from a height of 24.0 inches above the top of the storage cell and its impact on top of the storage cell legs.
By conservatively neglecting the piston effect as the fuel assembly falls through t}:.le storage cell, but considering buoyancy and drag effects, the velocity of impact has been calculated to be 30 feet per second.
It has been conservatively assumed that the fuel e.ssembly absorbs 30 percent of the kinetic energy of impact. Calculations using the Modi-fied Petri formula for :penetration of a "hard:' missile in a concrete target indicate that the storage cell legs may penetrate the concrete floor by approximately 3/4 inch. The ductile stainless steel liner plate will be stretched or 11 drawn' 1 into the resulting cavity. The maximum calculated plate strain for this condition has been calcula-ed as 72 percent of the .stainless steel ultimate strain capacity.
Thus, no tearing or perf*oration of the liner will occur.
The reaction load resu1ting from the deformation of the fuel assembly has been conservatively calculated using the fuel assembly axial stiff-ness and assuming a uni.form compression with buckling. This reaction load (186 Kip) results i,n concrete bearing* stress of 11. 6 ksi and a punching shear stress -:in the steel liner plate of 31.ksi indicating local crumbling of concrete under ideal "punch and die" support condi-tions which do not exist due to the support provided by the concrete underneath the liner plate.
It can, therefore, be concluded that the straight drop of a fuel assem-bly through a storage cell and its impact on top of the storage cell base legs would result in minor local crumbling of the concrete floor and a small acceptable deformation of the liner plate. However, the structural integrity of the storage rack and the leak tight integrity of the spent fuel storage pool will be maintained.
- RESULTS OF FUEL ASSEMBLY DROP ANALYSIS STRAIGHT DROP THROUGH CELL FROM 24 INCHES ABOVE CELL Allowable Value Weight of fuel Assembly, k
- J 1.6 Maximum Drop Height, in. 190.5 Free Fall Impact Velocity, ft/sec 32.0 Impact Velocity Considering Drag and Buoyant Forces, ft/sec 29.8 Kinetic Energy of Drop to be Absorbed by Fuel and Floor, in-k 268.3 Kinetic Energy Absorbed by Fuel Assembly Uniform Compression (assumed), % 30 Kinetic Energy Absorbed by Floor and Liner Plate (assumed), % 70 Maximum Transmitted Reaction Force, k 185.6 1
Maximum Concrete Bearing Stress, ksi 11.6 3. 57 , 2 Maximum Cell Leg Penetration into Concrete Pool Floor, in o. 76 3 Maximum Liner Plate Tensile Strain, in/in 0.35 0.485 Maximum Punching Shear Stress in Stainless 4 Steel Liner Plate, ksi 31.0 41.5
- 1. Based on Paragraph 10.14 of ACI 318-71
- 2. There will be local crumbling of the concrete under each leg
- 3. Strain at ultimate stress (Dynamic)
- 4. Dynamic Yield Stress for Stainless Steel
(.