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Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024 Integrated Inspection Report 05000443/2024003 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums ML24303A0352024-10-29029 October 2024 Operator Licensing Examination Approval IR 05000443/20244022024-10-17017 October 2024 Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only) L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024 Core Operating Limits Report for Reload Cycle 24 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes ML24254A2552024-09-25025 September 2024 Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24239A5382024-09-20020 September 2024 Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000443/20240052024-08-29029 August 2024 Updated Inspection Plan for Seabrook Station (Report 05000443/2024005) ML24232A1142024-08-21021 August 2024 Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024 Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024 Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent . IR 05000443/20240022024-08-0606 August 2024 Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001 L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024 Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024 Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite. ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations L-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 IR 05000443/20240102024-05-29029 May 2024 Biennial Problem Identification and Resolution Inspection Report 05000443/2024010 IR 05000443/20240112024-05-24024 May 2024 Age-Related Degradation Inspection Report 05000443/2024011 IR 05000443/20240012024-05-13013 May 2024 Integrated Inspection Report 05000443/2024001 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 ML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000443/20245012024-04-22022 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501 05000443/LER-2024-001, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024 Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024 To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) L-2024-037, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024 To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024 Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024 Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024 Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024 Radiological Emergency Plan (Ssrep), Revision 82 IR 05000443/20230042024-02-12012 February 2024 Integrated Inspection Report 05000443/2023004 ML24009A1152024-01-29029 January 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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) 2024-09-25
[Table view] 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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FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station 1603) 773-7000 NOV I 7 2003 Docket No. 50-443 NYN-03097 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 - 0001 Seabrook Station Cycle 10 Core Operating Limits Report FPL Energy Seabrook, LLC (FPLE Seabrook) is enclosing the Cycle 10 Core Operating Limits Report (COLR) for Seabrook Station pursuant to Technical Specification 6.8.1.6.c. Cycle 10 operation of Seabrook Station commenced on October 26, 2003.
Should you require further information regarding this report, please contact Mr. Paul V. Gurney, Reactor Engineering Manager at (603) 773-7776.
Very truly yours, FPL ENERGY SEABROOK, LLC
/ Jads M.Peschel eg latory Programs Manager cc: H. J. Miller, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate I-2 G. T. Dentel, NRC Senior Resident Inspector an FPL Group company
ENCLOSURE TO NYN-03097 C
RE-21 Rev. 01-10-00 Page 1 of 17 CORE OPERATING LIMITS REPORT SEABROOK STATION CYCLE 10 COLR June 2003 RE Supervisor 1W-3~~~~~~~~~~~~~~~~~~~~~
Operations Manager agi,
RE-21 Rev. 01-10-00 Page 2 of 17 1.0 Core Operating Limits Report This Core Operating Limits Report for Seabrook Station Unit 1, Cycle 10 has been prepared in accordance with the requirements of Technical Specification 6.8.1.6.
The Technical Specifications affected by this report are:
- 1) 2.2.1 Limiting Safety System Settings
- 2) 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4
- 3) 3.1.1.2 Shutdown Margin Limit for MODE 5
- 4) 3.1.1.3 Moderator Temperature Coefficient
- 5) 3.1.3.5 Shutdown Rod Insertion Limit
- 6) 3.1.3.6 Control Rod Insertion Limits
- 7) 3.2.1 Axial Flux Difference
- 8) 3.2.2 Heat Flux Hot Channel Factor
- 9) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.8.1.6.
2.1 Limiting Safety System Settings: (Specification 2.2.1) 2.1.1 Cycle Dependent Overtemperature AT Trip Setpoint Parameters and Function Modifier:
2.1.1.1 K1 =1.180 2.1.1.2 K2 = 0.021/ F 2.1.1.3 K3 = 0.0011 / psig T = Measured RCS Tag (0F ), and T' = Indicated RCS Tg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, < 588.5 0F ).
P' = Nominal RCS operating pressure, 2235 psig
RE-21 Rev. 01-10-00 Page 3 of 17 2.1.1.4 Channel Total Allowance (TA) = N.A.
2.1.1.5 Channel Z = N.A.
2.1.1.6 Channel Sensor Error (S)=N.A.
2.1.1.7 Allowable Value - The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 0.5% of AT span. Note that 0.5% of AT span is applicable to OTAT input channels AT, Tavg and Pressurizer Pressure; 0.25% of AT span is applicable to AI.
2.1.1.8 f 1(AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with nominal gains to be selected based on measured instrument response during plant startup tests calibrations such that:
(1) For q, - q betveen -20% and +4%, f(AI) 2 0; where q and q are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and q, + qb is the total THERMAL POWER in percent RATED THERMAL POWER; (2) For each percent that the magnitude of q, - q exceeds -20%, the AT Trip Setpoint shall be automatically reduced by 2 3.1% of its value at RATED THERMAL POWER.
(3) For each percent that the magnitude of q, - q exceeds +4%, the AT Trip Setpoint shall be automatically reduced by 2 2.44% of its value at RATED THERMAL POWER.
See Figure 5.
2.1.1.9 Ti 2 8 seconds 2.1.1.10 T2 3 seconds 2.1.1.11 ¶3 = Oseconds 2.1.1.12 14Ž 33 seconds 2.1.1.13 5
- 4 seconds 2.1.1.14 6 = Oseconds
RE-21 Rev. 01-10-00 Page 4 of 17 2.1.2 Cycle Dependent Overpower AT Trip Setpoint Parameters and Function Modifier:
2.1.2.1 K4 = 1.121 2.1.2.2 K5 = 0.020 / F for increasing average temperature and K = 0.0 for decreasing average temperature.
2.1.2.3 K6 = 0.00175 / IF for T > T" and K6 = 0.0 for T 5 T", where:
T = Measured Tag (IF ), and T" = Indicated Ta., at RATED THERMAL POWER (Calibration temperature for AT instrumentation, 5 587.5 0F).
2.1.2.4 Channel Total Allowance (TA) = N.A.
2.1.2.5 Channel Z = N.A.
2.1.2.6 Channel Sensor Error (S) =N.A.
2.1.2.7 Allowable Value - The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 0.5% of AT span. Note that 0.5% of AT span is applicable to OPAT input channels AT and Tag.
2.1.2.8 f2(AI) is disabled.
2.1.2.9 -rl as defined in 2.1.1.9, above.
2.1.2.10 T2 as defined in 2..190, above.
2.1.2.11 T as defined in 2.1.1.11, above.
2.1.2.12 T6 as defined in 2.1.1.14, above.
RE-21 Rev. 01-10-00 Page 5 of 17 2.1.2.13 7 10 seconds. It is recognized that exactly equal values cannot always be dialed into the numerator and denominator in the protection system hardware, even if the nominal values are the same (10 seconds). Thus given the inequality sign in the COLR (greater than or equal to) the intent of the definition of this time constant applies primarily to the rate time constant (i.e., the Tau value in the numerator). The lag time constant (denominator Tau value) may be less than 10 seconds or less than the value of the numerator Tau value (e.g., if the numerator is set at 10.5, the denominator may be set to 10 or 9.5) and still satisfy the intent of the anticipatory protective feature.
2.2 Shutdown Margin Limit for MODES 1, 2, 3, and 4: (Specification 3.1.1.1)
A) The Shutdown Margin shall be greater than or equal to 1.3% AK/K, in MODES 1, 2, 3.
B) The Shutdown Margin shall be greater than or equal to 2.2% AK/K, in MODE 4.
2.3 Shutdown Margin Limit for MODE 5: (Specification 3.1.1.2)
The Shutdown Margin shall be greater than or equal to 2.2% AK/K.
2.4 Moderator Temperature Coefficient: (Specification 3.1.1.3) 2.4.1 The Moderator Temperature Coefficient (MTC) shall be less positive than +3.12 x 05 AK/K/0 F for Beginning of Cycle Life (BOL), All Rods Out (ARO), Hot Zero Thermal Power conditions.
2.4.2 MTC shall be less negative than -5.0 x 104 AK/K/0 F for End of Cycle Life (EOL), ARO, Rated Thermal Power conditions.
2.4.3 The 300 ppm ARO, Rated Thermal Power MTC shall be less negative than -4.1 x 104 AK/K/0 F (300 ppm Surveillance Limit).
2.5 Shutdown Rod Insertion Limit: (Specification 3.1.3.5) 2.5.1 The shutdown rods shall be fully withdrawn. The fully withdrawn position is defined as the interval within 225 steps withdrawn to the mechanical fully withdrawn position inclusive.
RE-21 Rev. 01-10-00 Page 6 of 17 2.6 Control Rod Insertion Limits: (Specification 3.1.3.6) 2.6.1 The control rod banks shall be limited in physical insertion as specified in Figure 1. Control Bank A shall be at least 225 steps withdrawn.
2.7 Axial Flux Difference: (Specification 3.2.1) 2.7.1 The indicated AFD must be within the Acceptable Operation Limits specified in Figure 2.
2.8 Heat Flux Hot Channel Factor: (Specification 3.2.2) 2.8.1 FRTPQ = 2.50 2.8.2 K(Z) is specified in Figure 3.
2.8.3 W(Z) is specified in Figures 4.1 to 4.5 and in Table 1.
The W(Z) data is applied over the cycle as follows:
BU < 150 MWD/MTU, linear extrapolation of 150 and 2000 MWD/MTU W(Z) data 150
- BU < 4000 MWD/MTU, quadratic interpolation of 150, 2000, and 6000 MWDIMTU W(Z) data 4000 < BU < 8000 MWD/MTU, quadratic interpolation of 2000, 6000, and 10000 MWD/MTU W(Z) data 8000
- BU < 17000 MWDJMTU, quadratic interpolation of 6000, 10000, and 17000 MWD/MTU W(Z) data BU > 17000 MWD/MTU, linear extrapolation of 10000 and 17000 MWD/MTU W(Z) data 2.8.4 The FmQ(Z) penalty factor is 1.02.
RE-21 Rev. 01-10-00 Page 7 of 17 2.9 Nuclear Enthalpy Rise Hot Channel Factor: (Specification 3.2.3) 2.9.1 FNAII FNMI(RTP) x ( I + PF x ( I -P ))
where P = THERMAL POWER RATED THERMAL POWER.
2.9.2.a For FNMl measured by the fixed incore detectors:
FNm(RTP) = 1.536 for the VANTAGE+ (w/ IFMs) and RFA fuels.
2.9.2.b For FN" measured by the movable incore detectors:
FNtH(RTP) = 1.540 for the VANTAGE+ (w/ IFMs) and RFA fuels.
2.9.3 Power Factor Multiplier for FNAII = PF = 0.3 for all fuel types.
RE-21 Rev. 01-10-00 Page 8 of 17 Figure 1 Control Bank Insertion Limits Versus Thermal Power 225 173,225) (0.726225) 200 BANKB X 175 (0.0,188) 2175 (1.0,166
~150BA C,,
W2125 0
a O75 50
- 0 25 (0.216,0.0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
0.0 0.2 0.4 0.6 0.8 1.0 Fraction of Rated Thenml Power
/ T RE-21 Rev. 01-10-00 Page 9 of 17 Figure 2 Axial Flux Difference Operating Limits Versus Thermal Power 110 100 90 a) 80 0
0.
70 E
60 S-a) 50 10 a) 40 30 20 10 0
50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (%DI)
Note: %DI = %Al
r.f .
RE-21 Rev. 01-10-00 Page 10 of 17 Figure 3 K(Z) Versus Core Height 12 1
0.8 0.4 02 0
0 1 2 3 4 5 6 7 8 9 10 11 12 Core gt(Fetd)
RE-21 Rev. 01-10-00 Page 11 of 17 Figure 4.1 W(Z) Versus Core Height 150 MWD/MTU 1.50 1.45 1.40 1.35 1.30 L 1.25 1.20 1.15 1.10 1.05 1.00 I I I I I I I I I I r
0 1 2 3 4% 0 0 7 8 9 10 11 12 Core Height (Feet)
RE-21 Rev. 01-10-00 Page 12 of 17 Figure 4.2 W(Z) Versus Core Height 2,000 MWD/MTU 1.50 1.45 I 4 4 + 4 $ 4 4 4 4-4 1.40 F t444 9144- 4 1 I or
.L. .3 .
1.30 - - _ _
1.25 1.20 1.1 -is _
1.10
- 1. 00 - - I I 0 2 3 4 5 6 7 8 9 10 11 12 Core Height (Feet)
RE-21 Rev. 01-10-00 Page 13 of 17 Figure 4.3 W(Z) Versus Core Height 6,000 MWD/MTU
- 1. 50 - - -_
- 1. 45 - --
- 1. 40 -
. 35 I1. 30 - - - ___
N N 1 . 25
- 1. 20 I
- 1. 15 _ _ < _7 1 10
- 1. 05.
- 1. 00 ... .... .. L . - I 1. L n .* Ia- . . I. .
U 1 4 .5 4% 51) a Ij vy .LU L1 +/-4 Core Height (Feet)
- -. I I RE-21 Rev. 01-10-00 Page 14 of 17 Figure 4.4 W(Z) Versus Core Height 10,000 MWD/MTU I1.45 ~
. 40 IIIII
. 35 ~
I1.
25 ~
I1.20 I I1.15 - -_ _ _ _ _
. 10-1 . 05 ~
1.
0 1 2 3 4 5 6 7 8 9 10 11 12 Core Height (Feet)
RE-21 Rev. 01-10-00 Page 15 of 17 Figure 4.5 W(Z) Versus Core Height 17,000 MWD/MTU 1.50 1.40 1.35_
1.3 0 N 1 2 5 1.20 -
1.15 1.10
- 1. 05-12 Core Height (Feet)
RE-21 Rev. 01-10-00 Page 16 of 17 Figure 5 f 1 (AI) Function f (A I),
(percent)
-39.35, 60 60 28.59, 60
<t~~~~~~~4
__ 01rl/I2_
-50 -40 -30 -20 -10 0 10 20 30 40 A I Band (percent)
- t -
N RE-21 Rev. 01-10-00 Page 17 of 17 Table 1 W(Z, BU) versus Axial Height HEIGHT (Z) W(Z,BU)
(Feet) 150 2000 6000 10000 17000
____1___60__ MWD/MTU MWD/MTU MWD/MTU MWD/MTU MNVD1MTU S 1.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.80 1.3452 1.3085 1.2840 1.2931 1.3000 2.00 1.3255 1.2884 1.2659 1.2780 1.2852 2.20 1.3048 1.2671 1.2472 1.2629 1.2696 2.40 1.2836 1.2469 1.2299 1.2481 1.2534 2.60 1.2623 1.2333 1.2197 1.2334 1.2365 2.80 1.2396 1.2198 1.2112 1.2216 1.2226 3.00 1.2232 1.2062 1.1999 1.2098 1.2091 3.20 1.2139 1.1950 1.1880 1.1990 1.1979 3.40 1.2055 1.1865 1.1799 1.1918 1.1931 3.60 1.1965 1.1797 1.1733 1.1840 1.1916 3.80 1.1861 1.1749 1.1690 1.1753 1.1898 4.00 1.1781 1.1703 1.1636 1.1663 1.1870 4.20 1.1726 1.1646 1.1566 1.1586 1.1836 4.40 1.1661 1.1582 1.1504 1.1528 1.1793 4.60 1.1590 1.1512 1.1435 1.1462 1.1741 4.80 1.1512 1.1435 1.1359 1.1389 1.1679 5.00 1.1427 1.1351 1.1278 1.1309 1.1605 5.20 1.1336 1.1261 1.1191 1.1226 1.1528 5.40 1.1239 1.1165 1.1096 1.1134 1.1462 5.60 1.1137 1.1065 1.0991 1.1028 1.1408 5.80 1.1032 1.0958 1.0927 1.1025 1.1442 6.00 1.1021 1.0932 1.0930 1.1081 1.1523 6.20 1.1105 1.0998 1.1013 1.1200 1.1587 6.40 1.1166 1.1053 1.1100 1.1321 1.1641 6.60 1.1222 1.1100 1.1176 1.1435 1.1693 6.80 1.1275 1.1169 1.1273 1.1541 1.1748 7.00 1.1345 1.1259 1.1376 1.1635 1.1797 7.20 1.1435 1.1348 1.1465 1.1715 1.1827 7.40 1.1511 1.1427 1.1542 1.1780 1.1843 7.60 1.1575 1.1494 1.1606 1.1829 1.1842 7.80 1.1617 1.1546 1.1656 1.1862 1.1824 8.00 1.1669 1.1596 1.1691 1.1872 1.1789 8.20 1.1743 1.1659 1.1723 1.1871 1.1737 8.40 1.1809 1.1720 1.1769 1.1890 1.1668 8.60 1.1909 1.1776 1.1787 1.1897 1.1589 8.80 1.2030 1.1813 1.1774 1.1910 1.1595 9.00 1.2144 1.1915 1.1853 1.1973 1.1672 9.20 1.2247 1.2119 1.2065 1.2090 1.1800 9.40 1.2378 1.2306 1.2250 1.2231 1.2045 9.60 1.2597 1.2482 1.2431 1.2464 1.2280 9.80 1.2823 1.2758 1.2738 1.2746 1.2497 10.00 1.3021 1.3106 1.3129 1.3024 1.2710 10.20 1.3170 1.3407 1.3487 1.3284 1.2908 210.40 1.0000 1.0000 1.0000 1.0000 1.0000