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MONTHYEARML14232A6222014-09-0909 September 2014 Acceptance of Requested Licensing Amendment Request and Exemption Regarding Revised Reactor Coolant System Pressure-Temperature Limits Project stage: Acceptance Review ML14363A3672015-01-0909 January 2015 Request for Additional Information Regarding the License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Tempt Requirements Project stage: RAI SBK-L-15040, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-03-0909 March 2015 Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years Project stage: Response to RAI ML15084A3752015-04-0303 April 2015 Request for Withholding Information from Public Disclosure Regarding License Amendment Request 14-04 for Seabrook Station, Unit 1 (TAC Nos. MF4576 and MF4577) Project stage: Withholding Request Acceptance ML15128A1482015-06-0505 June 2015 Request for Withholding Information from Public Disclosure Regarding License Amendment Request 14-04 for Seabrook Station, Unit 1 Project stage: Withholding Request Acceptance SBK-L-15129, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-06-24024 June 2015 Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years Project stage: Response to RAI SBK-L-15132, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-07-0909 July 2015 Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years Project stage: Response to RAI SBK-L-15151, Supplemental Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-07-20020 July 2015 Supplemental Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years Project stage: Supplement SBK-L-15172, Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-09-0808 September 2015 Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years Project stage: Supplement ML15096A2552015-11-0202 November 2015 Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years Project stage: Approval 2015-04-03
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Category:Letter type:SBK
MONTHYEARSBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report SBK-L-22093, 75 Day and 150 Day Submittal Letters2022-12-0101 December 2022 75 Day and 150 Day Submittal Letters SBK-L-22113, Radiological Emergency Plan (Ssrep), Revision 792022-11-16016 November 2022 Radiological Emergency Plan (Ssrep), Revision 79 SBK-L-22114, Independent Spent Fuel Storage Installation (Isfsi), Cask Registration2022-11-0909 November 2022 Independent Spent Fuel Storage Installation (Isfsi), Cask Registration SBK-L-22112, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-11-0303 November 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22105, Supplement to 2021 Annual Radioactive Effluent Release Report2022-10-24024 October 2022 Supplement to 2021 Annual Radioactive Effluent Release Report SBK-L-22103, 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan2022-10-12012 October 2022 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan SBK-L-22102, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-10-0606 October 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22080, Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 20222022-08-12012 August 2022 Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 2022 SBK-L-22054, SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0909 June 2022 SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections SBK-L-22044, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 7822022-04-20020 April 2022 Radiological Emergency Plan (Ssrep), Revision 782 SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 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 SBK-L-21105, Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension2021-09-27027 September 2021 Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension SBK-L-21103, Request for Exercise of Enforcement Discretion2021-09-25025 September 2021 Request for Exercise of Enforcement Discretion SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension2021-09-25025 September 2021 Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21083, NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage2021-08-18018 August 2021 NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating Report SBK-L-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21042, Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-21023, Radiological Emergency Plan (Ssrep), Revision 772021-03-0404 March 2021 Radiological Emergency Plan (Ssrep), Revision 77 SBK-L-20154, Submittal of Changes to the Seabrook Station Technical Specification Bases2020-12-22022 December 2020 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20146, One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c2020-12-0303 December 2020 One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c SBK-L-20144, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-23023 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20143, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-022020-11-19019 November 2020 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-02 SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating SBK-L-20085, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-16016 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 2024-04-12
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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 . 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. ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 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, 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 L-2023-005, Response to Request for Additional Information for Seabrook Relief Request 4RA-22-0012023-01-26026 January 2023 Response to Request for Additional Information for Seabrook Relief Request 4RA-22-001 ML22307A1682022-11-0303 November 2022 Cover Memo and Response to C-10 Questions Regarding 2Q2022 Inspection Report - Corrected L-2022-157, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report2022-09-28028 September 2022 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report L-2022-106, Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-06-27027 June 2022 Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML22109A0342022-04-19019 April 2022 Cover Memo and Response to C-10 Questions Regarding 4Q2021 Inspection Report SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML21280A2622021-10-0707 October 2021 Response Letter to N. Treat (C-10 Research and Education Foundation) Regarding 2Q 2021 Integrated Inspection Report Questions SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request SBK-L-19120, Response to Request for Additional Information Related to Seabrook Inverter Amendment2019-10-30030 October 2019 Response to Request for Additional Information Related to Seabrook Inverter Amendment SBK-L-18106, Response to Requests for Additional Information Related to License Renewal Application Environmental Review2018-06-14014 June 2018 Response to Requests for Additional Information Related to License Renewal Application Environmental Review SBK-L-18074, Response to Request for Additional Information Regarding License Amendment Request 16-032018-06-0707 June 2018 Response to Request for Additional Information Regarding License Amendment Request 16-03 L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations SBK-L-18027, Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program2018-02-28028 February 2018 Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program2018-02-28028 February 2018 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program SBK-L-17202, Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption2017-12-14014 December 2017 Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption SBK-L-17204, Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)2017-12-11011 December 2017 Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) SBK-L-17180, Supplement 58, Revised Alkali-Silica Reaction Aging Management Program2017-11-0303 November 2017 Supplement 58, Revised Alkali-Silica Reaction Aging Management Program SBK-L-17169, Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-171552017-10-17017 October 2017 Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-17155 SBK-L-17170, Non-Proprietary Enclosure 1 to SBK-L-171562017-10-17017 October 2017 Non-Proprietary Enclosure 1 to SBK-L-17156 SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction2017-10-0303 October 2017 Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction2017-10-0303 October 2017 Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction SBK-L-17133, Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program2017-08-11011 August 2017 Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program SBK-L-17103, Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program2017-06-20020 June 2017 Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program SBK-L-17087, Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-05-25025 May 2017 Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components SBK-L-17082, Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components2017-05-19019 May 2017 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components SBK-L-17063, Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality2017-04-0808 April 2017 Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality SBK-L-16205, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-22016-12-30030 December 2016 Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-2 SBK-L-16196, Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...2016-12-15015 December 2016 Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive... SBK-L-16186, Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations2016-11-23023 November 2016 Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations SBK-L-16190, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-11-17017 November 2016 Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency ML16314D4272016-11-0707 November 2016 Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Submittal of Flooding Hazards Reevaluation Report, Revision 1 L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) SBK-L-16170, Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report2016-10-27027 October 2016 Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-10-27027 October 2016 Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2016-10-27027 October 2016 Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors SBK-L-16156, Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations2016-10-0707 October 2016 Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations SBK-L-16134, Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application2016-09-0606 September 2016 Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application SBK-L-16121, Response to RIS-16-09, Preparation and Scheduling of Operator Licensing Examinations2016-07-20020 July 2016 Response to RIS-16-09, Preparation and Scheduling of Operator Licensing Examinations SBK-L-16044, Response to Request for Information Regarding the Flooding Hazards Reevaluation Report2016-03-28028 March 2016 Response to Request for Information Regarding the Flooding Hazards Reevaluation Report 2024-08-12
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N ExTeraENERGY !,,.,-ýSEýAB ROýOK July 9, 2015 10 CFR 50.90 SBK-L-15132 Docket No. 5 0-443 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years
References:
- 1. Seabrook Station License Amendment Request 14-04, "Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years," SBK-L-14102, July 24, 2014 (ML14216A404).
- 2. NRC letter to Seabrook Station, "Seabrook Station, Unit No. 1 -Request for Additional Information Regarding License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Temperature requirements (TAC Nos. MF4576 and MF4577)," dated January 9, 2015 (ML14363A367).
- 3. Seabrook Station letter SBK-L-15040, "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years, dated March 9, 2015 (ML15072A036).
- 4. Seabrook Station letter SBK-L-15129, "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years, dated June 23, 2015.In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 14-04 to the Technical Specifications (TS) for Seabrook Station and requested an exemption from the requirements of 10 CFR 50 Appendix G. The proposed change revises the NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 U.S. Nuclear Regulatory Commission SBK-L- 15132/Page 2 pressure-temperature (P/T) limits in TS 3 /4.4.9 LCO 3.4.9.1, Reactor Coolant System Pressure-Temperature Limits, to be applicable to 55 effective full power years. The change also revises TS 3 /4/4.9 LCO 3.4.9.3, Overpressure Protection Systems, by providing new overpressure protection setpoints and lowering the RCS temperature at which the TS is applicable.
In Reference 2, the NRC requested additional information to complete its review of LAR 14-04.NextEra provided the responses to RAIs 2.1.1, 2.1.2, 2.1.3 and 2.1.4 in Reference 3 along with a request to extend its response to RAI 2.2.1 to June 30, 2015.The response to RAI 2.2.1 required additional input from the vendor to complete the response.In a conference call on June 17, 2015, the NRC requested an additional note be added to the Seabrook pressure-temperature curves restricting the heat-up rate to less than or equal to 20 'F per hour for moderator temperatures less than 120 'F. In Reference 4, NextEra requested additional time to obtain the requested information from its vendor, Westinghouse and to submit its response to RAI 2.2.1.The response to RAI 2.2.1 is provided in the enclosure to this letter. The revised marked-up technical specification pages are provided in the attachment to this letter.The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted License Amendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure /Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T) limits that are applicable to 55 effective full power years (EFPY). As a result, a No Significant Hazards Consideration was performed for the revised Pressure Temperature Limits in TS Figures 3.4-2 and 3.4-3.This letter contains no regulatory commitments.
Should you have any questions regarding this letter, please contact Mr. Michael Ossing, Licensing Manager, at (603) 773-7512.I declare under penalty of perjury that the foregoing is true and correct.Executed on July _\ ,2015.Sincerely, NextEra Energy Seabrook, LLC Ralph A. Dodds, III Plant General Manager Enclosure U.S. Nuclear Regulatory Commission SBK-L-15132/Page 3 cc: D. Dorman, NRC Region I Administrator J. Lamb, NRC Project Manager, Project Directorate 1-2 P. Cataldo, NRC Senior Resident Inspector Mr. Perry Plummer Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 ENCLOSURE to SBK-L-15132 Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years NRC RAI2.2.1.:
The current TS P-T limit curves for 23. 7 EFPY have margins to account for pressure and temperature instrument errors; the proposed 55 EFPY TS P-T limits do not have these margins.Please address how instrumentation errors will be accounted for to ensure that the RCS is operated in accordance with the proposed TS P-T limits for 55 EFPY NextEra Response: The proposed TS P-T limit curves for 55 EFPY have been revised to include margins to account for pressure and temperature instrument uncertainty.
Changes were also made to eliminate heat up and cool down rates that are not achievable during normal plant operating conditions in the lower temperature regions where the cold overpressure mitigation system (COMS) is enabled to protect the RCS with power operated relief valves (PORVs) as identified in TS Figure 3.4-4. No changes were made to the PORV set point values TS Figure 3.4-4 as this figure already contains appropriate instrument uncertainty as well as additional margins for pressure overshoot transients should an actuation occur.Specifically, the revised curves shift the heat up and cool down P-T Limits curve data points developed in WCAP-17441-NP by 100 psi downward and 20'F to the right to account for the instrument uncertainty.
An additional 15 psi uncertainty was applied to the heat up curve above the COMS enable temperature where operationally the wide range pressure indication on the main control board could be the only available indication in some unlikely but possible scenarios.
In addition to accounting for instrument uncertainty, unachievable heat up and cool down rates were eliminated or restricted.
For the heat up limitation curve, proposed TS Figure 3.4-2, a heat up rate restriction of 20°F/hr was added at temperatures at or below 120'F, corresponding to the transient defined in WCAP-17444 and the previous response to RAI 2.1.4. At temperatures greater than 120'F to less than 200'F the heat up rate of 80°F/hr maximum is specified and at greater than or equal to 200'F the maximum rate is 100°F/hr.
Instrument uncertainties of 20'F and 100 psi were added to the data points in WCAP-17441-NP Table 6-3. An additional pressure uncertainty of 15 psi was added to the heat up curve starting at 200'F prior to the cold overpressure mitigation system being disabled.
Considering the 20°F/hr rate restriction, pressure and temperature data from 60'F to 80'F (40°F to 60'F without the instrument uncertainty of 20'F) were determined using the more limiting pressure rate change between the existing 80°F/hr heat up data and the steady state data. Linear extrapolation of the 60'F to 65°F allowable pressure change of 13 psi per 5°F was applied to the heat up curve pressure limits from 60°F to 80'F.These heat up rate limitations and instrument uncertainties additions result in all pressure limitations at or below 225°F, in the COMS enable temperature region, being above and protected by the COMS system set point curve in TS Figure 3.4-4.For the cool down limitation curve, proposed TS Figure 3.4-3, the cool down rate is restricted to 20°F/hr at temperatures less than 150'F. Instrument uncertainties of 20'F and 100 psi were added to the data points in WCAP-17441-NP Table 6-4. Since the entire curve is to the left and above the COMS enable temperature and pressure limits identified in TS Figure 3.4-4, the additional 15 psi uncertainty was not Page 1 of 6 necessary.
Pressure and temperature data from 60'F to 80'F (40'F to 60'F without the instrument uncertainty of 20'F) were determined by linear extrapolation of the pressure rate change between 60'F to 65'F for the 20°F/hr cool down data and the steady state data which results in a 13 psi change per 5°F. These cool down rate limitations and instrument uncertainties additions result in all pressure limitations being above and protected by the COMS system set point curve in TS Figure 3.4-4.The bolt up temperature was maintained at 60'F as identified in WCAP-14040-A, Revision 4,"Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves." The limiting closure head region material RTndt is 30°F allowing bolt up temperature to be as low as 50'F with the application of uncertainty.
However, the 60'F bolt up temperature advised in WCAP-14040-A is maintained.
The proposed heat up limitation curve, TS Figure 3.4-2, and the proposed cool down limitation curve, TS Figure 3.4-3 applicable for 55 EFPY have been revised to include margins to account for pressure and temperature instrument uncertainty as described above and are provided in the attachment.
The revised data points for the revised heat up and cool down curves are provided in Tables 1 and 2 respectively.
Page 2 of 6 Significant Hazards Consideration No Significant Hazards Consideration:
The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted License Amendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure /Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T)limits that are applicable to 55 effective full power years (EFPY). As a result, a No Significant Hazards Consideration was performed for the revised Pressure Temperature Limits in TS Figures 3.4-2 and 3.4-3.In accordance with 10 CFR 50.92, NextEra Energy Seabrook has concluded that the proposed change does not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed change does not involve a SHC is as follows: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
No. The proposed changes to the Technical Specifications (TS) do not impact the physical function of plant structures, systems, or components (SSCs) or the manner in which SSCs perform their design function.
Operation in accordance with the proposed TS will ensure that all analyzed accidents will continue to be mitigated by the SSCs as previously analyzed.
The proposed changes do not alter or prevent the ability of operable SSCs to perform their intended function to mitigate the consequences of an initiating event within assumed acceptance limits. The proposed changes neither adversely affect accident initiators or precursors, nor alter design assumptions.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
No. The proposed changes do not involve installation of new or different type of equipment, create new failure modes for existing equipment, or create any new limiting single failures.
The changes to the pressure -temperature limits will continue to ensure that appropriate fracture toughness margins are maintained to protect against reactor vessel failure, during both normal and low temperature operation.
The proposed changes are consistent with the applicable NRC approved methodologies (i.e., WCAP-14040, Rev. 4 and ASME Code Case N-641). Plant operation will not be altered, and all safety functions will continue to perform as previously assumed in accident analyses.Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
Page 3 of 6
- 3. Does the proposed change involve a significant reduction in the margin of safety?No. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed changes will not adversely affect the operation of plant equipment or the function of any equipment assumed in the accident analysis.
The proposed changes were developed using NRC approved methodologies and will continue to ensure an acceptable margin of safety is maintained.
The safety analysis acceptance criteria are not affected by this change. The proposed changes will not result in plant operation in a configuration outside the design basis. The proposed changes do not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.Based on the above, NextEra concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(b), and, accordingly, a finding of"no significant hazards consideration" is justified.
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{Aj Fc aq oj sju!od muj I alqui Table 2 Data Points for the 55 EFPY Seabrook Unit 1 Cooldown Curves using the 1998 through the 2000 Addenda App. G Methodology (with Kic, without Flange Notch, and with Margins for Instrumentation Errors)Steady-State 2 0 1F/hr Cooldown 100°F/hr Cooldown (0 0 F/hr)T P P P (OF) (psig) T (0 F) (psig) T (0 F) (psig)60 0 60 0 60 577 60 537 65 590 65 550 70 603 70 563 75 616 75 576 80 629 80 589 85 642 85 602 90 656 90 618 95 671 95 635 100 689 100 654 105 708 105 674 110 729 110 697 115 752 115 723 120 778 120 751 125 806 125 782 130 838 130 817 135 872 135 855 140 911 140 897 145 953 145 944 150 1000 150 995 150 995 155 1052 155 1052 160 1109 160 1109 165 1172 165 1172 170 1242 170 1242 175 1319 175 1319 180 1404 180 1404 185 1499 185 1499 190 1603 190 1603 195 1718 195 1718 200 1846 200 1846 205 1986 205 1986 210 2142 210 2142 215 2314 215 2314 220 2504 1 220 2504 Page 6 of 6 Attachment to SBK-L- 15132 Marked-Up Technical Specification Pages 11v!SeRT-A (A/X 7 itC L --- L 1 --I- J , -I-.. T-r ---.--1 TL ----i ea estI I I I I I I I iI Linaccepta
' ceptable S Operati T,, .operation
-Hea Rate [ ticaI irnit 80 Deg. F/Hr 1 0DegF~r.L+/-.
I IL.J, L.S Heatu I I I I I Ia Imit I I 100 g. F/ -r ----i- -'-- --- " -FR-r IL A I II I iiI Ii I I Ii tr I --I--I4 -I eP 4I-t I l tI l i-I- T -T 1-----Z --...1000 -/" A/ii._.I lO00 I, 300 IRE (Deg. F, gI8 500 UP 0 23.7 EFPY/O /E tFE SEABROOK -UNIT 1 3/4 4-23 SEABROK -UNIT 3/44-23Amendment No. 19, 89, 115,13-5 Insert A MATERIAL PROPERTY BASIS LIMITING MATERIAL:
Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1 LIMITING ART VALUES AT 55 EFPY: 1/4T, 117°F (Axial Flaw)3/4T, 105'F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors 2500 2250 _ _ I Leak Test Limit 2000 -_ _1750 " 170Critical Limit IHeatup Curve-- 1500 Unacceptable IOperation I CLI a
_ 1250 .---p, U)Heatup rate below rn- 1000 --120 F shall not -- , _-_ exceed 20OF/hr -Composite Heatup Curve 750 Indicated RCS Maximum Alloy (fl Temperature Heatup Rat T5 <120°F 20F/hr O ------ 200'F > T > 120°F 8 0°F/hr'50 250 0 0 50 100 150 200 250 300 350 400 450 500 550 RCS Temperature (Deg. F, 10 Deg. F per division)* Curve is Applicable for RCS Vacuum fill FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS
-APPLICABLE UP TO 55 EFPY 1,4,YW re(x-r F A, ej V 1 AERIAL PR ERTY BASIS Limiting erial: LOWER 5 ELL P/LATE -,1808-1ART values a 3.7 EFPYI/4 , 109'F 4T, 88 0 P Curves appli lr the firs EFFY and ntain margin 20'F and 100 ig for possib instrument error-,onon --"-./ //80 2600 -2400 2200 -2000 1800 -w IL S160 CD* 1400-CO)120 S1000-0-600 200-r 1 -- -------1. -1'3rT- -r- -------I/ I I I I .ptable II IIII peration --j.4 .L __- -_ -J ------- ------- ----------
--I-------, ----Co -ldown ta Uplo g I I I-- ---I ,-----------
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-- '---, -I--P- --II I I I ----- --iI I I l t-l ...I -T r 7-- Cool n Rates t L ~ f...A L....L.i -....c Deg.F/Hr -, 2 I I I I I I I I I I-e. -,- -- ----- -- -----4.JWLJ. 80, 100 D .F/hr JIIAI JI -LJ L -..h-I-I I I I I I I I I I I I I I£ _ I £ I I! _ I I I I i I i J 'I I I I B I pI I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I II I I I I I I I I I II I I I I I I I I m pI I I I I I I I I I I I I I III I I I I I I I I I 1 I I//11/, 71 0 100 200 300 400 500 R TEMPERAT (Deg. F, 2 eg. F PER DV ION)GURE 3.4-3 ACTOR COO T SYSTEM OLDOWN LI11 ATIONS -LICABLE UP 23.7 EF Y SEABROOK -UNIT 1 3/4 4-24 Amendment No. 19, 89, 115, 135 Insert B MATERIAL PROPERTY BASIS LIMITING MATERIAL:
Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1 LIMITING ART VALUES AT 55 EFPY: 1/4T, 1177F (Axial Flaw)3/4T, 1057F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors 2500 2250 2000 1750 C 0> 1500 CL 0)0 1250 CL 0 Lo)1000 750 5)C,)W~ 500 F neptable Lgperaionj Li..Acetable I I t F--Composite Cooldown Curve Indicated RCS Maximum Allowable Temperature Cooldown Rate T < 150°F 20°F/hr T > 150°F 100°F/hr 250 0 I ..I ....I ....I .. ..0 50 100 150 200 250 300 350 400 450 500 550 RCS Temperature (Deg. F, 10 Deg. F per division)* Curve is Applicable for RCS Vacuum fill FIGURE 3.4-3 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS
-APPLICABLE UP TO 55 EFPY