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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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NEXTera ENERGY ~
SEABROOK SBK-L-21056 May 20, 2021 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Docket No. 50-443 Seabrook Station Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review
References:
- 1. NextEra Energy Seabrook, LLC letter SBK-L-20127, "Steam Generator Tube Inspection Report", October 20, 2020 (ML20295A551).
- 2. NRC "Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review", April 07, 2021 (ML21097A251).
In Reference 1, NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) submitted the 2020 Steam Generator Tube Inspection Report required by Technical Specification (TS) 6.8.1. 7, which provided the results of the steam generator tube inspections conducted during Refueling Outage (RFO) 20 in April 2020.
In Reference 2, the NRC requested additional information to complete their evaluation of the information provided within Reference 1.
The enclosure provides NextEra Energy Seabrook's response to the NRC's Request for Additional Information (RAI).
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
SBK-L-21056 Page2 If you have any questions regarding this correspondence, please contact Mr. Matthew Levander, Licensing Manager, at (603) 773-7631.
No new or revised commitments are included in this letter.
Executed on May 20, 2021.
Sincerely, Ne;;zt:'g~LC Matthew Levander Licensing Manager Enclosure cc: NRG Region I Administrator NRG Project Manager NRG Senior Resident Inspector
Enclosure to SBK-L-21056 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review
Enclosure to SBK-L-21056 Page 1of5 By letter dated October 20, 2020 (Agencywide Documents Access and Management System Accession No. ML20295A551), NextEra Energy Seabrook, LLC (the licensee) submitted information summarizing the results of the spring 2020 steam generator (SG) tube inspections performed at Seabrook Station, Unit No. 1 (Seabrook) during refueling outage 20 (OR20).
In reviewing the submitted information, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is necessary to complete its review.
Responses to the requests for additional information (RAI) are provided below.
Note: A list of the acronyms and abbreviations used in the responses to the RAls is provided in the last section of the Enclosure.
RAl-1:
Appendix B of the report states that review of the eddy current data from previous inspections identified discernable signals for some of the axial outside diameter stress corrosion cracking (ODSCC) indications detected at dented tube support plate intersections during the OR20 inspection in spring 2020. Cracking at tube geometric changes, such as dents, can be difficult to detect due to the presence of masking signals. The report states that the signals were not identified as flaw signals during the previous inspections. For those axial ODSCC indications at dented tube support plates in OR20 that had discernable signals in previous inspections, please provide the following:
- a. Describe the analysis approach, including techniques and historical data review, that led to the conclusion that cracks were present in the dented locations.
- b. For each crack indication, using the new analysis protocol developed in 2020, identify the inspection in which a flaw signal was first discernable.
- c. Discuss the lessons learned from the 2020 inspections and any actions being taken to increase the probability of detecting similar cracks in future inspections.
- d. Please discuss any insights about relative eddy current probe performance and the importance of supplemental inspections. For example, Table 2 of the report shows ODSCC indications in adjacent tubes (Row 10 Column 121 and Row 11 Column 121) at dents with bobbin probe voltage less than two volts. Both indications were classified as bobbin probe distorted dent signals and +Point' single axial indications, but the array probe detected only one of them.
Seabrook Station Response to RAI -1:
- a. During OR20, the bobbin probe analysis approach for dents at structures was as follows:
Per the dent/ding flowchart in the bobbin ETSS, signals measuring :::;175 degrees on Channel P1 (or if an ID indication is present in the dent) are to be reported as DOI (distorted dent indication). Analysis instructions also allow the data analysts to report "OSI" (distorted support indication) from channel P1 if the signal is distorted and flaw-like. The data analysis guidelines instruct the data analysts to review history from the oldest bobbin data digitally available for each SG (OR5/0R6).
As discussed in Section A of the OR20 SG Tube Inspection Report (Reference 1), dents >5 volts were part of the +Point' special interest exams. For most of the dented locations examined, the signal from the dent was straight-forward and not distorted. In those cases, the resolution analysts assigned the "no degradation found" (NDF) reporting code. Except
Enclosure to SBK-L-21056 Page 2 of 5 for the dent in tube R16C5 at 08H, all the dents associated with crack-like indications in OR20 were traceable to preservice inspection data with no change in voltage (amplitude).
The dent in tube R16C5 at 08H first appeared in the 1997 data and measured at 0.95 volts.
The dent indication in tube R 16C5 at 08H reached the ;::: 2 volts bobbin probe reporting criteria in OR20 (see Table 2-1 below) and had a small distorted signal that had obviously changed from the 1997 data, and was assigned a "distorted dent indication" (DOI) code.
The +Point' probe exam of the location also showed a strong/clear (high POD) SAi indication. This 2020 indication in tube R16C5 heightened sensitivity during the inspection to the analysis of dented locations with complex +Point' probe signals. It was judged that this could be indicative of possible ODSCC at the dented locations. Although the other tubes in SG-8 with bobbin dent indications did not exhibit the obvious change from the 1997 bobbin data as evident in tube R16C5, they all had fairly complex +Point' signals. Due to the discovery of the confirmed SA ls in R 16C5 at 08H, the resolution analysis team agreed the most conservative approach was to report (as SAls) all +Point' probe indications at dented structures that had distorted +Point' signals.
- b. Using the approach of reviewing the earliest available +Point' historical data, initial signal formation for the SAls reported in OR20 was observed as follows:
Location Flaw signal first Row Col elevation discernable in 10 121 OSH+0.31 OR20 11 121 08H+0.4 OR15 14 119 OSH+0.51 OR15 15 120 OSH-0.63 OR15 OSH+0.41 OR15 16 120 OSH-0.45 OR15 13 120 OSH-0.37 OR15 OSH+0.49 OR15 14 120 OSH-0.42 OR15 15 119 OSH+0.61 OR15 OSH+0.63 OR15 16 119 OSH-0.33 OR15 OSH+0.51 OR20 16 5 OSH-0.48 OR20 42 102 OSC-0.51 OR17
- c. The key lessons learned for Seabrook from the 2020 SG inspections are as follows:
Use earliest available +Point' data for historical comparison: During the OR20 ECT exams, historical +Point' data was available for use by the resolution analysts to review/compare flaw-like signals; however, the resolution analysis instructions did not specify the inspection year's data to use for that review. As a result, the process lacked clear guidance for performing historical lookbacks of +Point' coil data so that indications showing discernable signals may be identified at the earliest opportunity. In future inspections, resolution analysis instructions will require the resolution analysts to use the earliest available +Point' data when reviews are performed. Industry guidance
Enclosure to SBK-L-21056 Page 3 of 5 including a flow-chart for TSP Dent analysis is also being revised by SGMP to emphasize the year of data to be used for historical reviews.
Ensure ECT analysts are trained to recognize complex low-level signals: This lesson was the main take-away from the SAi reported in the tube at R16C5 at 08H (described in the response to Item a. of RAl-1). Some complex dent/crack-like indications could potentially be mischaracterized since the dent and/or lift-off signals may affect some potential flaw signals. Future ECT analysts taking the site-specific performance demonstration (SSPD) training prior to a SG inspection will be trained to identify distorted +Point' signals that could potentially be ODSCC at the dented locations.
Seabrook has provided the OR20 crack-like indications and historical crack-like data back to 2012 to EPRI SGMP for posting on EPRlq.com so that other plants can include the data signals in their SSPDs for future inspections.
- Analysts should also use multiple channels to diagnose dents at structures: The %
prime frequency differential channel (bobbin coil) has typically been used to determine if a free-span ding indication had changed from history. A review of OR20 results show that the change of dent-related indications at structures was more evident when using the % prime frequency differential channel. This experience was provided to the EPRI SGMP and is being used to develop guidance to further aid ECT resolution analysts in the detection of a signal change (when compared to historical data) for dent indications at structures.
- d. The DDS indications in tubes R10C121 and R11C121 at 08H were reported in OR20 at 2.41V and 4.06V, respectively; corrected information is provided in Table 2-1 below. Since the array probe has limited EPRl-qualified Appendix H/I techniques, technique extension was used for different regions of interest (ROls) in the Seabrook SGs in OR20 including axial ODSCC at dented TSPs. ETSS 20402.1 Rev 5 was justified for the array probe to be extended for axial ODSCC at dents at structures up to 7.5 volts. The array probe employs an array of non-surface riding coils and has less sensitivity to small surface imperfections (compared to surface-riding RPC probes like +Point') as the probe passes through the tube. It is plausible that this characteristic may be the underlying reason for the discrepancy in the array probe results for the indications that were sampled in OR20.
The array probe results obtained in OR20 during Appendix H/I technique extension, highlight the importance of using multiple probe types during diagnostic/special interest and supplemental exams. Even though the array probe may be qualified for the application, a confirmatory reading with the +Point' probe at "dents at structures" is recommended during future inspections for Seabrook based on the experience from the OR20 SG ECT exams.
RAl-2:
Table 2 shows that the detected cracks had bobbin probe voltages either less than 2 volts or greater than about 9 volts. Please describe how this distribution for crack indications compares to the distribution of all bobbin probe dent voltages (i.e., dents with and without cracks), and whether any correlation was identified between cracking and bobbin probe dent voltage.
Enclosure to SBK-L-21056 Page 4 of 5 Seabrook Station Response to RAI - 2:
Correction to reported information: In Table 2 of the OR20 SG Tube Inspection Report (Reference 1), four indications were inadvertently denoted with bobbin dent sizes "<2V" instead of "'5:.5V". Corrected information for these indications is provided in Table 2-1 below along with the actual reported bobbin dent voltages.
Table 2-1 Location Bobbin dent Row Col elevation size voltaae in OR20 Code 10 121 08H+0.31 '5:.5V 2.41V DDS 11 121 08H+0.4 '5:.5V 4.06V DDS 08H+0.51 '5:.5V 2.16V DOI 16 5 08H-0.48 '5:.5V 1.13V OSI Response to RAl-2: As shown in Table 2 of Reference 1, the OR20 crack-like indications at dents had bobbin probe reporting codes: DOI/OSI, DDS and ONT. In the analysis below, for each type of bobbin dent code reported, the bobbin probe dent sizes of crack-like indications are compared with the distribution of bobbin probe dent sizes at the uppermost TSP.
DOI: Only one other bobbin DOI was reported on a tube without cracks. It was in the cold leg (08C) and measured 2.13V by the bobbin probe. The 2.13V is of the same order of magnitude as the single 2.16Von the crack-like indication (see Table 2-1 above). It was also noted that the bobbin DOI on the non-cracked tube was also on a peripheral tube like the OR20 crack-like indications. (OSI: Although OSI is not a dent reporting code, for completeness, it should be noted that no other bobbin OSI indications were reported in the top TSP during the OR20 inspection.)
DDS, ONT: The remaining OR20 crack-like indications were classified as bobbin DDS (HL only) and bobbin ONT (HL, CL). The population distribution of reported bobbin probe dent voltages in the top TSP is summarized in Table 2-2 below:
Table 2-2 Bobbin code Elevation Total Ranae (Volt) Median Mean Std Dev DDS 08H 156 0.62-4.65 2.48 2.64V 0.88 ONT 08C 175 2.25-19.24 7.24 8.01V 3.22 ONT 08H 105 2.1 - 16.01 6.91 7.18V 2.81 Referring to Table 2 of Reference 1 and Table 2-2 above, the following observations are noted:
- For the two crack-like indications reported as DDS by bobbin in OR20 (Table 2), the bobbin probe dent voltage of one was closer to the mean of the distribution; the other was closer to the top of the voltage range. It was also noted that the tube with the SAi reported at R10C121 (Table 2) also had a non-cracked bobbin DDS reported at the lower edge of the TSP. Although not crack-like, the DDS at the lower edge reported the highest bobbin probe dent voltage (4.65V) of the entire DDS population at 08H.
- For the single crack-like indication reported in the CL (Table 2), the bobbin probe ONT voltage was close to the mean of the distribution.
Enclosure to SBK-L-21056 Page 5 of 5
- The remaining 10 crack-like indications coded as bobbin ONT in the HL in OR20 (Table
- 2) were all ?:.9V, and above the mean and median of the bobbin probe dent voltage distribution. The largest cracked dent voltage (16.01 V) was also the highest voltage in the distribution of all bobbin probe ONT voltages at 08H.
RAl-3:
The report identifies volumetric wear indications from tube support plates in SG-C and SG-D that were newly reported in OR20 but had discernable signals in previous inspections according to historical data review. Two of the indications had depths of 23 and 28 percent through-wall when first reported in OR20. Please describe the site reporting requirements for volumetric indications relative to these indications.
Seabrook Station Response to RAI - 3:
The bobbin coil reporting requirements for indications at tube support plates (TSPs) in the OR20 Bobbin ETSS were to report "OSI" from Channel P1 if the signal is distorted and flaw-like.
Channel P1 is a 2-channel mix that is designed/utilized by the data analyst to mix out the tube support response from the calibration standard's TSP ring, and output only the flaw component of the signal. The Channel P1 mix does not always completely mix out the TSP component of the mix channel output; therefore, some TSP residual may remain, making detection of low-level wear challenging.
This was the case for the 2 newly reported TSP wear indications in OR20. A bobbin OSI of 0.19V was reported for the indication in SG-C (R6C39). A historical review showed that the indication was visible back to the 2006 inspection with very little change between 2006 and 2020. A bobbin OSI of 0.33V was reported for the indication in SG-D (R5C100). Historical review showed that the indication was visible in 2018 with a very slight change from 2018 to 2020. The +Point' sizing results (23%, 28%) of the two indications are likely overly conservative.
Abbreviations and Acronyms:
CL Cold Leg NDF No Degradation Found DOI Distorted Dent Indication ODSCC OD Stress Corrosion Cracking DDS Distorted Dent Signal POD Probability of Detection ONT Dent ROI Region of Interest OSI Distorted Support Indication RPC Rotating Pancake Coil ECT Eddy Current Testing SAi Single Axial Indication EPRI Electric Power Research Institute SG Steam Generator ETSS Exam Technique Spec Sheet SGMP SG Management Program HL Hot Leg SSPD Site-Specific Performance ID Inside Diameter Demonstration NOD No Degradation Detectable TSP Tube Support Plate