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MONTHYEARML16230A1822016-09-0101 September 2016 Proprietary Information Determination Project stage: Other 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 Project stage: Request ML16277A5492016-10-13013 October 2016 Regulatory Audit Plan - Alkali Silica Reaction Aging Management Program, Regarding Seabrook Station, Unit 1, License Renewal Application Review Project stage: Other ML16301A4282016-11-14014 November 2016 Requests for Additional Information for the Review of the License Renewal Application Project stage: RAI 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 Project stage: Response to RAI ML16326A0372016-11-30030 November 2016 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application Project stage: RAI ML16333A2472016-12-21021 December 2016 Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal Project stage: Other ML17017A3742017-02-27027 February 2017 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16342C4672017-03-0101 March 2017 12/01/2016 Summary of Teleconference Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Requests for Additional Information Pertaining to the Seabrook Station License Renewal Application Project stage: RAI ML16341B9022017-03-0707 March 2017 03/07/2016 Summary of Telecon Held on Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Request for Additional Information Pertaining to the Seabrook Station License Renewal Application Project stage: RAI ML17066A4882017-03-16016 March 2017 Steam Generator ISG RAI for the Review of the Seabrook Station License Renewal Application Project stage: RAI ML17088A6142017-03-29029 March 2017 Request for Additional Information for the Review of the Seabrook Station License Renewal Application Project stage: RAI ML17139B8352017-05-24024 May 2017 Final Request for Additional Information Regarding Seabrook License Renewal Application - Set 26 Project stage: RAI ML17357A0452017-05-24024 May 2017 2017/05/24 Seabrook La - Seabrook Station, Unit 1 Final Request for Additional Information Regarding Seabrook License Renewal Application Set 26 Project stage: RAI 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 Project stage: Response to RAI ML17309A0692017-06-0505 June 2017 2017/06/05 Seabrook La - Summary of Meeting Held on May 9, 2017, Between the U.S. Nuclear Regulatory Commission Staff and Nextera Energy Seabrook, LLC, Representatives to Discuss the Seabrook Station, License Renewal Application Project stage: Meeting SBK-L-17102, Clarification to Supplement 53 - Response to Request for Additional Information for the Review of the License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-06-20020 June 2017 Clarification to Supplement 53 - Response to Request for Additional Information for the Review of the License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components Project stage: Response to RAI 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 Project stage: Response to RAI 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 Project stage: Supplement ML17262A3742017-12-0808 December 2017 Project Manager Change for the License Renewal of Seabrook, Unit 1, License Renewal Application Project stage: Other ML18254A2942018-09-28028 September 2018 Safety Evaluation Report Re License Renewal of Seabrook Station Unit 1 Project stage: Approval ML18254A2812018-09-28028 September 2018 Final SER Project stage: Request ML18254A2932018-09-28028 September 2018 Safety Evaluation Report Re License Renewal of Seabrook Unit 1 Project stage: Approval ML18362A3702019-01-0202 January 2019 Safety Evaluation Report Re License Renewal of Seabrook Station Unit 1. Supersedes ML18254A294 Project stage: Approval ML18345A1202019-03-12012 March 2019 Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 Project stage: Request ML18345A1212019-03-12012 March 2019 Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 Project stage: Approval ML18345A2322019-03-12012 March 2019 Federal Register Notice - Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 Project stage: Approval ML19205A3902019-07-24024 July 2019 NRC042 - Letter from Tam Tran, NRC, to Eric Mccartney, NextEra, Alkali Silica Reaction Monitoring Aging Management Program Audit Report Regarding the Seabrook Station, Unit 1, License Renewal (CAC No. ME4028) (Dec. 21, 2016) Project stage: Other 2017-03-01
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Category:Letter type:SBK
MONTHYEARSBK-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-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating 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 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 2023-06-22
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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 ML16067A1642016-02-26026 February 2016 NextEra Response to NRC 12/23/2015 Request for Additional Information for ASR Ceb and RHR Vault SBK-L-16022, Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction2016-02-23023 February 2016 Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction SBK-L-15202, Transmittal of Response to Requests for Additional Information for the Review of the License Renewal Application - Set 25, Relating to the Alkali-Silica Reaction2015-12-0303 December 2015 Transmittal of Response to Requests for Additional Information for the Review of the License Renewal Application - Set 25, Relating to the Alkali-Silica Reaction 2023-08-07
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SEABROOK June 20, 2017 10 CFR 54 Docket No. 50-443 SBK-L-17103 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program
References:
- 1. NextEra Energy Seabrook LLC, letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010 (Accession Number ML101590099).
- 2. NRC, "Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Set 26 (CAC NO. ME4028), RAI B.2.1.9 Bolting Integrity," May 24, 2017 (Accession Number ML171398835).
- 3. NextEra Energy Seabrook LLC, letter SBK-L-12258, "LRA Commitment Update and RAI B.1.4-4 Clarification," December 10, 2012 (Accession Number ML12349A214).
In Reference 1, NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) submitted an application for a renewed facility operating license for Seabrook Station Unit 1 in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51 , and 54.
In Reference 2, the NRC requested additional information related to NextEra Energy Seabrook's Bolting Integrity Program and how the aging effects for closure bolting associated with air filled, gas filled, and systems at atmospheric pressure will be managed.
NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road, Seabrook, NH 03874
U.S. Nuclear Regulatory Commission SBK-L-17103 I Page 2 In Reference 3, Nextera Energy Seabrook submitted letter SBK-L-12258, which revised License Renewal Application Appendix A, A.2.1 .9, and Appendix B, B.2.1.9. provides NextEra Energy Seabrook's response to the NRC's Request for Additional Information (RAI B.2.1.9-3) concerning closure bolting aging management for air filled , gas filled, and systems at internal atmospheric pressure. provides NextEra Energy Seabrook's revision of License Renewal Application, Appendix B - Aging Management Programs , B.2.1 .9 - Bolting Integrity.
The enclosures include changes to the LRA. To facilitate understanding , the changes are explained, and where appropriate, portions of the LRA are repeated with the change highlighted by strikethroughs for deleted text and balded italics for inserted text.
There are no new or revised regulatory commitments contained in this letter.
If there are any questions or additional information is needed, please contact Mr.
Edward J. Carley, Engineering Supervisor - License Renewal, at (603) 773-7957 .
If you have any questions regarding this correspondence, please contact Mr. Kenneth Browne, Licensing Manager, at (603) 773-7932 .
I declare under penalty of perjury that the foregoing is true and correct.
Executed on June '2.0 , 2017.
Sincerely, NextEra Energy Seabrook, LLC
Enclosures:
- Supplement 55 - NextEra Energy Seabrook's response to RAI B.2 .1.9-3.
Enclosure 2: Supplement 55 - Revision of License Renewal Application, Appendix B -
Aging Management Programs, B.2.1 .9 - Bolting Integrity.
U.S. Nuclear Regulatory Commission SBK-L-17103 I Page 3 cc: D. H. Dorman NRC Region I Administrator J.C. Poole NRC Project Manager P. C. Cataldo NRC Senior Resident Inspector L. M. James NRC Project Manager, License Renewal 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 perry.plummer@dos.nh.gov Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 John.Giarrusso@massmail.state.ma.us
Enclosure 1 to SBK-L-17103 Supplement 55 - NextEra Energy Seabrook's response to RAI B.2.1.9-3.
U.S. Nuclear Regulatory Commission SBK-L-17103 I Enclosure 1/ Page 2 RAI # 8.2.1.9-3
Background
Section 54.21 (a)(3) of 10 CFR requires the applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. As described in SRP-LR, an applicant may demonstrate compliance with 1* 0 CFR 54.21 (a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.
GALL Report AMP Xl.M18 states:
Degradation of pressure boundary closure bolting due to crack initiation, loss of preload, or loss of material may result in leakage from the mating surfaces or joint connections of pressure boundary components. Periodic inspection of pressure boundary components for signs of leakage ensures that age-related degradation of closure bolting is detected and corrected before component leakage becomes excessive. Accordingly, pressure retaining bolted connections should be inspected at least once per refueling cycle.
LRA Section B.2.1.9 states that the Bolting Integrity program "includes periodic inspection of closure bolting assemblies to detect signs of leakage that may be indicative of loss of preload ...
Periodic inspection of bolted closures in conjunction with the Seabrook Station In service Inspection Program and Seabrook Station External Surfaces Monitoring Program will detect the aging effects and joint leakage." The LRA states that the External Surfaces Monitoring and In service Inspection programs use visual inspections to detect leakage which could indicate a loss of preload for closure bolting.
Issue While the staff notes that visual inspections will be capable of detecting leakage of liquid filled systems, a visual inspection may not be sufficient to detect leakage for air- or gas filled systems.
LRA Table 3.3.2-8, "Containment Online Purge System," and 3.3.2-20, "Instrument Air System,"
are examples of systems that cite the Bolting Integrity Program to manage aging effects associated with closure bolting that could be or are air-filled or gas-filled. Based on a review of LRA Section B.2.1.9 and SER with Open Items Section 3.0.3.1.7, "Bolting Integrity," it is not clear how aging effects for closure bolting installed in air-filled or gas-filled systems will be effectively managed because in these systems there is typically limited or no visual signs of leakage.
NRC Request #1 For air-filled systems, gas-filled systems, and systems at internal atmosphere pressure for which aging effects for closure bolting will be managed by the Bolting Integrity Program, state how the aging effects will be managed.
U.S. Nuclear Regulatory Commission SBK-L-17103 I Enclosure 1/ Page 3 NextEra Energy Seabrook's Response to RAI B.2.1.9-3, Request #1 NextEra Energy Seabrook's Plant Leak Management procedure provides a means of identifying, classifying, and tracking external, non-boric acid system leaks. The Leak Management procedure includes using suitable leak detection, evaluation, correction and prevention techniques to not only try to prevent leaks from occurring in the first place, but how to assess and address them if they do occur. Within the Station's leak management procedure, air and gas filled system leaks are identified using a soap like solution to produce bubbling at the leakage location. Alternative methods can include, but are not limited to, audible leak detection (with normal listening or enhanced utilizing ultrasonic leak detection), staining, performance monitoring parameters (pressure, temperature, H2 detectors, etc.), or use of helium for vacuum leaks in certain applications. Seabrook will manage aging effects for Bolting Integrity closure bolting in air and gas filled systems by using leak identification and correction to preclude loss of intended function.
For Bolting Integrity program closure bolting associated with systems at internal atmospheric pressure, Seabrook will perform a tightness check on in-scope and readily accessible closure bolts prior to the period of extended operation. A tightness check, combined with good leak management and bolt torqueing practices, will manage the aging effects of closure bolting associated with systems at internal atmospheric pressure within the Bolting Integrity program.
The revised License Renewal Application, Appendix B - Aging Management Programs, B.2.1.9 - Bolting Integrity, Program Description, is presented within Enclosure 2 of this letter.
U.S. Nuclear Regulatory Commission SBK-L-17103 I Enclosure 1/ Page 4 NRC Request #2 State any enhancements to plant-specific procedures and/or to the Bolting Integrity program necessary to incorporate how these aging effects will be managed.
NextEra Energy's Seabrook Response to RAI B.2.1.9-3, Request #2 The revised License Renewal Application, Appendix B -Aging Management Programs, B.2.1.9 - Bolting Integrity, Program Description, is presented within Enclosure 2 of this letter.
As discussed in response to Request #1 within this letter, the current Seabrook Station Plant Leak Management procedure will be utilized for aging management of in scope closure bolting of the Bolting Integrity program associated with air and gas filled systems. For systems at internal atmospheric pressure, a tightness check will be performed on readily accessible in scope closure bolting prior to the period of extended operation.
Enclosure 2 to SBK-L-17103 Supplement 55 - Revision of License Renewal Application, Appendix B - Aging Management Programs, B.2.1.9 - Bolting Integrity.
U.S. Nuclear Regulatory Commission SBK-L-17103 I Enclosure 2/ Page 2 Enclosure bolting of air filled, gas filled, and systems at atmospheric pressure within the Bolting Integrity program will have the appropriate aging management. As transmitted previously in SBK-L-12258 (Reference 3), the second paragraph of Seabrook Station's License Renewal Application, Appendix B - Aging Management Programs, B.2.1.9 -
Bolting Integrity, Program Description, second paragraph, is revised below.
The program includes periodic inspection of closure bolting assemblies to detect signs of leakage that may be indicative of loss of preload, loss of material, or crack initiation. Leak detection inspections are performed on in scope closure bolting in air filled and gas filled systems using a method that detects leakage. Prior to the period of extended operation, readily accessible closure bolting within systems at internal atmospheric pressure will have a tightness check performed. Periodic inspection of bolted closures in conjunction with the Seabrook Station lnservice Inspection Program and Seabrook Station External Surfaces Monitoring Program will detect the aging effects and joint leakage.
Operator rounds and system walkdowns will also identify joint leakage. Bolted connections in buried, underground, and inaccessible submerged piping will be inspected for indication of leakage caused by loss of preload when the associated piping is inspected by the Buried Piping and Tanks Inspection program. In instances where hydrostatic testing, flow testing, or fire protection jockey pump monitoring are used in lieu of visual inspections, these methods will also be credited to identify leakage caused by loss of preload at bolted connections. Additionally, the service water pump column bolted connections are submerged in raw water and cannot be inspected for leakage due to loss of preload.
Service water pump column bolting will be inspected for loss of material and loss of preload when the service water pumps are removed for maintenance.