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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Report
MONTHYEARL-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 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-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant ML22124A0112022-04-30030 April 2022 Scoping Summary Report - Final L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI2022-01-14014 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld2022-01-12012 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout L-2021-178, Report of 10 CFR 50.59 Plant Changes2021-11-0808 November 2021 Report of 10 CFR 50.59 Plant Changes L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML19252A4002019-09-0909 September 2019 FPL to NRC, Notification of Smalltooth Sawfish Capture at St. Lucie 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 ML18096B3952018-04-0606 April 2018 Exhibit III Estimate of Construction Costs and Exhibit IV Technical Qualifications of Contractors ML18088B1952018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 9, Auxiliary Systems and Chapter 10, Steam and Power Conversion System ML18088B1942018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 11, Radioactive Waste Management System, Chapter 12, Radiation Protection, and Chapter 13, Conduct of Operations ML18088A0942018-03-29029 March 2018 Unit II Plants ECCS Performance Results L-2017-173, Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event2017-09-28028 September 2017 Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event L-2018-081, Kld Engineering, Pc - 2017 Population Update Analysis2017-09-20020 September 2017 Kld Engineering, Pc - 2017 Population Update Analysis L-2017-117, Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-12017-06-20020 June 2017 Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-1 L-2018-015, Plan of Study 316(b) Implementation2017-04-28028 April 2017 Plan of Study 316(b) Implementation L-2017-015, PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee.2016-04-30030 April 2016 PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee. ML16084A6162016-03-24024 March 2016 Submittal of Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant, Units 1 and 2 in St. Lucie County, Florida ML16063A0072016-02-26026 February 2016 Participation in Additional Work Under the Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 PA-MSC-0983 R2 Cafeteria Task 8 and Acceptance Criteria for Measurement Of.. ML15352A0532016-01-0707 January 2016 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 L-2015-297, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan2015-12-10010 December 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. ML15314A1602015-10-29029 October 2015 St. Lucie, Units 1 and 2 - License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program L-2015-221, Report of 10 CFR 50.59 Plant Changes2015-10-16016 October 2015 Report of 10 CFR 50.59 Plant Changes ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 L-2015-143, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-05-14014 May 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 20152015-05-0808 May 2015 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 L-2016-052, TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182.2015-03-31031 March 2015 TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182. L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report ML15083A2642015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report2015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-125, Report of 10 CFR 50.59 Plant Changes2014-05-0606 May 2014 Report of 10 CFR 50.59 Plant Changes ML13360A2022013-12-12012 December 2013 EPA Echo Report Martin County, Fl 2023-09-28
[Table view] Category:Technical
MONTHYEARL-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI2022-01-14014 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld2022-01-12012 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 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 ML18096B3952018-04-0606 April 2018 Exhibit III Estimate of Construction Costs and Exhibit IV Technical Qualifications of Contractors ML18088B1942018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 11, Radioactive Waste Management System, Chapter 12, Radiation Protection, and Chapter 13, Conduct of Operations ML18088B1952018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 9, Auxiliary Systems and Chapter 10, Steam and Power Conversion System ML18088A0942018-03-29029 March 2018 Unit II Plants ECCS Performance Results L-2018-081, Kld Engineering, Pc - 2017 Population Update Analysis2017-09-20020 September 2017 Kld Engineering, Pc - 2017 Population Update Analysis L-2018-015, Plan of Study 316(b) Implementation2017-04-28028 April 2017 Plan of Study 316(b) Implementation L-2017-015, PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee.2016-04-30030 April 2016 PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee. ML16084A6162016-03-24024 March 2016 Submittal of Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant, Units 1 and 2 in St. Lucie County, Florida ML16063A0072016-02-26026 February 2016 Participation in Additional Work Under the Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 PA-MSC-0983 R2 Cafeteria Task 8 and Acceptance Criteria for Measurement Of.. L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 20152015-05-0808 May 2015 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 L-2016-052, TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182.2015-03-31031 March 2015 TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182. L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14149A1952013-02-0404 February 2013 Pacific Northwest National Laboratory Technical Letter Report for Evaluation of Alternative to 10 CFR 50.55a(G)(6)ll)(F)(4) for Limitations to Volumetric Examination of Dissimilar Metal Welds ML12340A3522012-11-30030 November 2012 St. Lucie, Unit 1, 12Q4116-RPT-001, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic L-2012-427, Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic2012-11-30030 November 2012 Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic ML12097A2682012-04-17017 April 2012 Biological Assessment for Formal Section 7 Consultation at the St. Lucie Plant, Units 1 and 2 L-2012-072, ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 32012-02-29029 February 2012 ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 3 ML12061A2492012-02-29029 February 2012 ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill L-2012-072, ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill2012-02-29029 February 2012 ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill L-2011-471, ANP-3057(NP), Revision 0, St. Lucie Unit 1 EPU - Responses to NRC Questions SRXB-58, SRXB-59, and SRXB-60.2011-10-31031 October 2011 ANP-3057(NP), Revision 0, St. Lucie Unit 1 EPU - Responses to NRC Questions SRXB-58, SRXB-59, and SRXB-60. L-2011-389, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-09-22022 September 2011 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request L-2011-311, ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 22011-08-31031 August 2011 ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 2 L-2011-342, ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb)2011-08-31031 August 2011 ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb) L-2011-228, 103-87735, Heated Water Plan of Study2011-06-30030 June 2011 103-87735, Heated Water Plan of Study L-2011-206, ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 72011-05-31031 May 2011 ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 7 ML11153A0492011-05-31031 May 2011 ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6 L-2011-206, ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 62011-05-31031 May 2011 ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6 L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix D, List of Key Acronyms2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix D, List of Key Acronyms L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods ML1107302992011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Licensing Report L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix a Safety Evaluation Report Compliance2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix a Safety Evaluation Report Compliance L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix F, Camereron Ultrasonics Engineering Reports, Cover2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix F, Camereron Ultrasonics Engineering Reports, Cover L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Feature Actuation, and Control Systems2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Feature Actuation, and Control Systems L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix G, Holtec Report No. HI-2104753, St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix G, Holtec Report No. HI-2104753, St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5, Appendix C, Grid Stability Analysis and System Impact Study for St. Lucie Plant with Proposed EPU2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5, Appendix C, Grid Stability Analysis and System Impact Study for St. Lucie Plant with Proposed EPU 2022-04-13
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Text
NRC FORM 196 U .S. NUCLEAR REGULATORV COMMI~ DOCKET NIJM QE R I2-78) 50-335 FILE NUMBER NRC DISTRIBuTION LLDR PART 50 DOCKET MATERIAL TO; ~ ~ ZIEMANN FROM: FLORDIA PWR & LIGHT CO. DATE OF DOCUMENT R.E. UHRIG 10-30-76 MIAMI, FLORDIA DATE RECEIVED 10-29-76 QLETTER CINOTORJZEO PROP INPUT FORM NUMBER OF COPIES RECEIVED SORIGINAL SUNCLASSIFIED C3COPV DESCRIPTION ENCLOSURE TR. RE. THEIR 6-30-76 LTR...,..TRANS THE FOLLOWI G SEISMIC ANALYSIS OF CON'fAINMENT FAN COOLER, UNITS ~ ~ ~ ~ ~ ~ ~
( 1 SIGNED CY. RECEIVED)
( 21 PAGES)
ACKNO~@Z)g@D i PLANT NAME: ST. LUCIE // 1 SAFETY FOR ACTION/INFORMATION B 11-3-76 ASSIGNED AD: ASSTI:fJED AD.
BRANCH CHIEF:
PROJECT >fANAGER: PRO NA ~
LIC ~ ASST DIGGS INTERNAL OISTRI BUTION 8 FIL SYSTEMS SAFETY SITE A NRC PDR HEINEMAN ENV 0 N I & E 2 SCHROEDER BENAROYA OELD GOSSICK & STAFF ENGINEERING, IPPOLITO MIPC MACCARRY KRKW 0 CASE KNIGHT HANAUER SIHWEIL OPERAT N REACTO S E PAWLICKI PROJECT MANA EhIEN REACTOR SAFEffY OPERA N BOYD ROSS EISENH P COLLINS NOVAK SHAO HOUSTON ROSZTOCZY BAER PETERSON CHECK BUTLER MELTZ R MES ifELTEMES, AT&I SKOVHOLT SALTZMAN RUTBI'.RG EXTFRNn I OISTnIBUTION CONTROL NUMBER LPDR: FT. PIERCE NAT LAB: BROOKffA TIC: REGS VIE ULRIKSON ORNL BASIC. LA PDR CONSULTANTS 10903 ASL~B' TO ACRS CAT NRC FORM 108 {2 78)
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POWER & LIGHT COMPANY 6'LORIDA 1I 5eclhe OeeEe> Clek August 30, 1976 L-,76-31 Office of Nuclear Reactor Regulation
'ttn: Dennis L. Ziemann, Chief Operating Reactors Branch N2 <@g qg6 Division of Operating Reactors U. S. Nuclear Regulatory Commission I Washington, D. C. 20555
Dear Mr. niemann:
ill~~
Re: St. Lucie Unit No. 1 (Docket No. 50-335)
Seismic Anal sis of Containment Fan Cooler Units Enclosed herewith is the document entitled "Seismic Analysis Report of the St. Lucie Unit 1 Fan Coolers." This document supplies information regarding the analytical techniques which were employed in the seismic analysis of the contain-ment fan cooler units at St. Lucie Unit No. l.
We are submitting this information in accordance with our commitment made in my letter of June 30, 1976 (L-76-243) and referred to in the Staff's Safety Analysis supporting Amend-ment No. 6 to the St. Lucie Unit 1 Operating License.
Very truly yours, Robert E. Uhrig Vice President.
REU/NR/hlc Attachment cc: Norman C. Moseley, Region XX Jack R. Newman, Esq.
e PEOPLE... SERVING PEOPLE
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- 8. PamkTe 6, A Ba'tetvgy,s o a, .e, ng enn~r
'tructure) 7pchiill0gg V~esgknghovse Efactetc Ca~ot'ation August t976
BURE Phfif ScJlcl!8ttc RGpwst".AtoHQA Qf tJ'l8 Pari General .AssemMy Rom Response Sp~ctra far Yarhjcal 0]F&C'L'~Pl ggE ~yg 0 s~g GB1Ap'Ing Floor Response Spot;%ra'or Ye&fcal Qfrect;]0@> @BE and 1C Damping f>abr Response Speci.re for Horizontal 9<rNt]en> QBK md 1'j Dlorp1ng " Kiev. 60
- 'F)4~0<'e~pons"., Speccwa f'r HoHzvntel UfmeMon68K e>~d 0 6% Damping - Kiev. 60
.6 f'~0M'5j>OM8 Sp&Ct'vh fQY'QY'1zoIABl .10 Dkmcclon, OBj AAl1 9.5N Pawpfng - Oav. 44
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'"44's'fs w@s perfo~4 40 Mcl"~fg Cl~ strgcfUM) )n(Gql"ltd 404 opcNbtl)cg Of'he St, Lucre - Unft 7 reactor conta$ nment fan cao'los+> w~hen sub$ er.'t~A to se<sv$ cI lo<<ds It was found fry~ the sefsm/c en@)ys$ s that the reactor centa<nm nt fan coo)qrs conform ta the St,. huc3s - Unky 1 seiom<r, cr$ ter$ e~
Prllented fn AM@ docvr@nt we the results fv0c the se38mtc analysts 4eranstvatfng th0 89fSmfc structumT adaqMCCy And op raMlfty 0f'he St. l,vCfe-Unht 7 f<n eQOTers Also, given <0 0 df cussfan Of ghe anelytfza.'l m.thods avyToged~ e deseetpC>ori: 0f the Input used, and e dhsevfpHon Of the fan cogent s4a~etuVek System.
T"< 9enere> ess@ublh'"<9 >SchePQt'fc O'Ag,) ct)n )g4
~ of'n 085eRL)]y, tM&f.or base, end heat exchenget's'senbly, The miami )s mounted on top of motor heat o
exchanger as,squab'fy sh$ r;h 3s baal ted td fan assembly, The eo!np'l~>te e~sembly' fs welded to the f'IMl'auAdeUon, The spacff/e, deaf;a<l< a("0 dian>ssed bolos,,
the fan assemb'lg qqnsksts of vAt0v 85aeab)y, hous)ng aa~emblv, beyHng base~,
inlet, spherical roHGr bee~tngs, Anl inlet flange ruing, Housfn<} ~s,se(ably $ '
mode ot <..)der steel plates <nd cona<ets of s)de sheets end scroll. 'fbi r'otor consists of cent>'<fogy> h3H'oH'bladed aha l assembly and the shaft, The wheel ossamh7y fs presseL an the EeP.end $ s also retained on the shaf't by'oto 3(4-30 sof', eeeewsi The tphet'Ical reklev beer fngs ere taunted orL V>e rotor assembly and bolted t0 the tearfng heae eseer4)y', The rotor ass,ebb'ly )s connected to the motor N$ th a fkexfbke coVpHhg<< Th heaving base fs febrfcated using u.lAd steel eonFereegerr. The Inlet $ s a$ etl ee'fded'teel construct'ion and ts used to gvjde ale $ Ate the >Week 6'ssek$ y, The vota> hose <s.ot a3) m7del eoostmeHon and CGNpor@onted so tb0t hat air 4 b<0<v over. the heat exchanger end rater'n~d to cool i'alar t~hfch
r~&ntfng Aa;aa $ ns<<4 the rotor bess.
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RECTA)H 8 N8f YTkCAL >KtH99$ AND CRklEArA A<<4e>et'<6e" ~n the praviovS serMon, they@ fs na $ ntaract$ w between the f'eA end @~toe stows of the fan can>ei" stt"vctut~ bee>Use each vector has ibS Ows fkxad Haring and'I@ sh4fts ata coaaectef through c> flex/hie ccupNne, Based oq.Ches feel, Ch. fan end motor M~r~ 'indqpendeqQy snblyped bdaAngs fox the &eetot'on&$ wenc f46 cool'm @am Used to 6etenv$ ne 44>. genera) assmBy, NL "nylons,, and p~cperQes 0& eeepwents.
)fan fthm@ StVQQCVLO Wit 4@49)64 48 Sph'fng N5SC SgstPAS and the Ahtgr'g fr6$ 0&n~."fag wve ee~vte4 td deb."nafne who behavior Qf the ep".,:ponents duHng seismic QxC]tent'fGFt. Ac c~k@fnC4 3A 880ttcn 4, t4 Qcpktftc@t'(on 1~'.v&1,$ 5F6 46tel'O'In&d based on, <he fleer wsp~se spectra, $ t ups deII;.,nntged that thG fwquqnc/qs essuehate4 trkt4 the f~<<vrator system knrlu@ng eel'fs and ~;oft banks have f ., .. -.$ pjw .* ~qff,.<<-
+)gpyya (gal p~$ pg plP ygp, g~$ + f n~+41gclh~
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~ewi.'. inat~en. e0 ey~sat<ng 'toads, h0~<sdntal se/size (ME], i(er t)ca7 eyfsmte (DBF), end acc<4mC pressure> (ee$ $ s and eye't bw>klan, L'tN'fC v4ttkss U$ 54 4 p8 fA. occgt46ncQ @th ttM 8148ttr. pr0vfgfcns fn P4r't, 7 (fan F00'lm et~tu~eE Ce.-~oheatj)ALSO-69 and ONE Sec. AU, Pmssvt'e vessels Spacif)eetions (ee)) tuba and If'stertor't), No anely+3s was nde f'r tt>e G8E sing fC v~s shme 4f@>t the DBE airless 'levels, are althing> 0N clast/e,
)frbktS, AR '685AM fA &0 Cf N8Ha c4CLWhts abON, I'i, )a lr)P,.~g
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., tlat) gj8'5/+'S5'b'$ "$Q"Ih't!6A Qlh~H'0 HPii't0 ki1lf illicit titC dpiIQGi'iOAS AYP 'IllflitCd old Mf)l ~ee$ n qkthkn ok>evabte values of'he apemttny c1eeronces I
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Ll 4 SKY ION INPUT DESCPIPTIOg Yhc sef$ r fc dcsfgo va'tush used fn th< c~lrglgtfang parL~ Dbthtjt~id /tarn 'thy' lac~ respon"e spectre foc1vded Tn the EWSCp sparest'<r.at<a>> cant:1g)geng An coofedS Koi FLO-8770,$ 76, datpd !4y 2g, lyy1, Sqqgfan 18 fn ~f9QM> ~ EQ ~ kffe th0 f700p rqgpgnr~g spectra gyp Ogp Figures. g
~rtd 3 6~'@ vert"tc".I f)GQl" Atspgn86 Kpectl"8 tor 0.5/, gqd 'lh gqgqpg~gg dygp)ng
<<I<<~>> t."~<p<<t'<<>4" ~~gums 4 and ~ ~~a haH~aot~1 <tool response spectra fOr Q,QX and lg equfpgng g~mpfgg velum, resp4gtf~<p'tg~ at reuetar bug1gftyg elevstfon 69. F)gushes 6 en6 7 eve hmfzon41 floov i.a<ponce spal;tr0 foe 0'.5l and 7A equfpneog d~fttg vhtu85> Yespectfvely, at meeter" bgtldfng .
01evat.ion 44, Ae shaw in FigvNg 4 4o 7> the msponsa speetN$ pebks are at and above Q.M scoop peafowl, 4ese thon or l.'gus tc 9.06 second par)ad Q3l:h 4t:tvdes
.a)1 nr.,Cut'e1 f~equacctas ca'tculatad for th(a essetk'fy,. the re;pansy ~ppotpa1, velr~e.. 0="vc converged to tt% fIMt acca7eraf.!on Va'toes, Consequently, th.,
'gseqgAy zan be eons$ dared es sighed tee Ch. floor mspans~ spectra shee fn Figures 8 to 7. Bomvav> for the purpose af conse~ett8m,. staffs acct)Lretkon~
of 0,6g and 0.4g for horteon541 And Vertfcal dfrectkonsvespeztfvely,.have been t".boson as the 08K kopvt ta the e+~sembly.
To o6Mcn the acxfiwm hypathetfcx1 ea<hquake (09E) values, the Nb0ve values ware tt;uktfpHed by 8, The foHaÃng 08K ar;celerztfon values t et"e vs@:
VEHTImL SEIS~ri HQRIMllTAL SE SNIC Oev. 44'lav
. 't. Rg M',2g The yartJea3~nd haHzont~1 ee$ @tfq Iood: vita applied.s<eAteneously to'aIIa~
f'Ot the worst pqss.)ge ~ongtfons, In audit;fan, the eo)hs mm sub)ected to a dfffaientihl presume of 2 pet to t-epr'est.nt the bIoefwA tvansfent pyeshvre d!4fer'ence.
vpp ~i %w'p,' flrwrt';; y'v.'+ "~.w,",h. s'~kl'itt'>~ri ~9~ri~ii>>'o"s "'. ws'M: ~,1,"ir.r>>>
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FIGURE 3: F)oo' kespome Spectia far'erkjeA N~tAm, QSK and N 9appin I
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F(GVRE 5; F'taor Response Spec".ra Ae Honzonw1 .Nrectite, RE and 0,5.'-: Oampir'q Hev. 69
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SECTION 9 0
~BEAU TS The fan'motor syst6N spl"fAg coo Canis and nafurg1 feequewieg ~i e cafculatod, A ShCÃt )n Tab'te 't, F11 enturo1 frequene.les are hbov~ .
80 Hz ftlcIQ'tng C4~~ Y'Cfbl" assBNbfg Nh'feb $ 8 24.6 Hg. Th95A fi"e<>u~nc<es are at end @&~vs the r)0/d range of the floor reepon~e spectra, (Ffgu&t, 3 tb 'F), f,e>> the fleer response spa<'.f;I"0 t,'converge Co She coARCBAt response value$ Qtth Le'ro ntap73fkatfon Ot and above. 20 Hz (qr Q,05 haec.),
Hecaus 6'f', neural f'~v>nc)es are tn the rept'an of zero nmpIlfkatfan the fan 600m'os(em [As 8Mfyzed using se'i$ ~~)c equfvaleot 854t~c loads.
840"fn ffl TGNQ R8 C4 c43cu1QC@f 5fld 73NIC betlav'Iov'1DAg (f/Ch of .sCvi~tlgth fov (fffferenf,'tNde$ i 086 setsmtc toads tR;r'e used to, thF'0ig'trl catty'tete the values 6 'faMe P., $ $ nce the clast/c Iieet<~ a~roe/send wk4h 0R 08K CvcftC 'NRM FIGC oxc&Ade0 ckeo DBE s6fsNfL favell MM usod, ft, $g t'ibt. necesggqr t@ p@pfeN an 08K grprsW<e analysts.
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