Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement
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MONTHYEARML1006401882010-03-0505 March 2010 Charter for the Groundwater Contamination Task Force Project stage: Request SBK-L-10077, Application for Renewed Operating License2010-05-25025 May 2010 Application for Renewed Operating License Project stage: Request ML1016203312010-06-0101 June 2010 Drawing LR-001 Through Drawing PID-1-CO-LR20423, Rev. 14 Project stage: Request ML1016203332010-06-0101 June 2010 Drawing PID-1-CO-LR20426, Rev. 30, Through Drawing PID-1-DW-LR20600, Rev. 11 Project stage: Request SBK-L-10095, Drawing PID-1-MAH-LR20497, Rev. 9, Through Drawing PID-1-SF-LR204822010-06-0101 June 2010 Drawing PID-1-MAH-LR20497, Rev. 9, Through Drawing PID-1-SF-LR20482 Project stage: Request ML1016203342010-06-0101 June 2010 Drawing PID-1-DW-LR20601, Rev. 1, Through Drawing PID-1-MAH-LR20496, Rev. 12 Project stage: Request ML1016203292010-06-0101 June 2010 Drawing PID-1-SF-LR20483, Rev. 15, Through Drawing PID-1-WT-LR20041, Rev. 7 Project stage: Request ML1016803692010-06-17017 June 2010 Commission Memorandum and Order (CLI-10-14) Project stage: Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides Project stage: Meeting ML1024200372010-08-19019 August 2010 Comment (1) of Maggie Hassan on Behalf of Constituents Different Opinion on the Relicensing of Seabrook Nuclear Power Plant Project stage: Request ML1025202072010-08-19019 August 2010 Transcript for Evening Public Scoping Meeting ISO Seabrook LRA SEIS Project stage: Request ML1025201832010-08-19019 August 2010 Transcript for Afternoon Public Scoping Meeting ISO Seabrook LRA SEIS, August 19, 2010. Pp 1-88 Project stage: Request ML1025002712010-08-23023 August 2010 Comment (2) of William R. Harris, on Behalf of Self, on Nextera Energy Seabrook, LLC Application for Renewal of License for Seabrook Project stage: Request ML1024200432010-08-25025 August 2010 Comment (3) of William Harris, Additional Reference Document for Seabrook Relicensing Environmental Review - Threat Assessment of Emp for Critical Infrastructure Project stage: Request ML1024505252010-09-0101 September 2010 Comment (4) of Geordie Vining on Behalf of Himself Opposing Relicensing Seabrook Plant for the Years 2030-2050 Project stage: Request ML1026504862010-09-20020 September 2010 Comment (6) of Joseph W. Fahey on Behalf of Amesbury on Environmental Impact & Mitigation Scoping for Relicensing of the Seabrook Nuclear Plant Project stage: Request ML1026403712010-09-20020 September 2010 Comment (6) of Joyce Kemp, Opposing NRC-2010-0206-0002, Environmental Impact Statements; Availability, Etc.: Nextera Energy Seabrook; Seabrook Station (Unit 1) Project stage: Request ML1026603312010-09-20020 September 2010 Comment (7) of Andrew R. Port on Behalf of City of Newburyport Office of Planning & Development on Environmental Scoping Review Regarding Application for an Operating License Extension for Seabrook, Unit 1 from Year 2030 to Year 2050 Project stage: Request ML1025202222010-09-20020 September 2010 Summary of Public License Renewal Overview and Environmental Scoping Meeting Related to the Review of the Seabrook Station License Renewal Application (TAC No. ME3959 and ME4028) Project stage: Meeting ML1028612172010-10-29029 October 2010 Request for Additional Information for the Review of the Seabrook Station License Renewal Application Environmental Review Project stage: RAI ML1030808802010-11-0404 November 2010 Letter from Nhdes to NextEra Energy Seabrook Czma Compliance for the Seabrook LRA Project stage: Request ML1030700562010-11-0808 November 2010 Environmental Project Manager Change for the License Renewal of Seabrook Station, Unit 1 Project stage: Other ML1029502712010-11-10010 November 2010 10/05-07/2010-Summary of Site Audit Related to the Review of the License Renewal Application for Seabrook Station, Unit 1 Project stage: Approval ML1030902152010-11-16016 November 2010 Request for Additional Information for the Review of the Seabrook Station License Renewal Application-SAMA Review Project stage: RAI ML1033701692010-11-23023 November 2010 Attachment 2, Vol. 2, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1033603262010-11-23023 November 2010 Attachment 2, Vol. 6, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI SBK-L-10185, Attachment 1 to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report.2010-11-23023 November 2010 Attachment 1 to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report. Project stage: Response to RAI SBK-L-10190, Response to Request for Additional Information, Submittal of Cultural Resource Plan in Accordance with 36 CFR 800.11 (C)2010-11-23023 November 2010 Response to Request for Additional Information, Submittal of Cultural Resource Plan in Accordance with 36 CFR 800.11 (C) Project stage: Response to RAI ML1033506392010-11-23023 November 2010 Seabrook Station - Response to Request for Additional Information - NextEra Energy Seabrook License Renewal Environmental Report Project stage: Response to RAI ML1101003122010-11-23023 November 2010 Attachment 2, Vol. 1, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1101003112010-11-23023 November 2010 Attachment 2, Vol. 1, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1033701672010-11-23023 November 2010 Attachment 3 to SBK-L-10185 -Seabrook Station Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Environmental Report Project stage: Response to RAI ML1033700922010-11-23023 November 2010 Attachment 2, Vol. 3, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1033603112010-11-23023 November 2010 Attachment 2, Vol. 2, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1033603062010-11-23023 November 2010 Attachment 2, Vol. 4, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1033603002010-11-23023 November 2010 Attachment 2, Vol. 7, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1033602982010-11-23023 November 2010 Attachment 2, Vol. 5, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit Project stage: Response to RAI ML1029806932010-12-21021 December 2010 Summary of Telephone Conference Call Held on 10/21/10 Btw the USNRC and NextEra Energy Seabrook, LLC, Concerning the Request for Additional Information Pertaining to the Seabrook Station License Renewal Application Project stage: RAI ML1033602122010-12-31031 December 2010 NUREG-1437 Supplement 38 Vol 2, (3:3) Appendix A-761 - End Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 Public Comments Project stage: Other ML1033602092010-12-31031 December 2010 NUREG-1437 Supplement 38 Vol 2, (2:3) Appendix A-454 - A-760 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 Public Comments Project stage: Other ML1033504382010-12-31031 December 2010 NUREG-1437 Supplement 38 Vol 2, (1:3) Cover - Appendix A-453 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 Public Comments Project stage: Acceptance Review ML1033504422010-12-31031 December 2010 NUREG-1437 Supplement 38 Vol 3 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3, Public Comments Continued, Appendices Project stage: Acceptance Review ML1035704012011-01-0303 January 2011 12/21/2010-Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning the RAI Pertaining to the Seabrook Station, License Renewal Application Project stage: RAI SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal Application2011-01-13013 January 2011 Response to Request for Additional Information, NextEra Energy License Renewal Application Project stage: Response to RAI SBK-L-11031, Environmental Permit Renewals2011-02-18018 February 2011 Environmental Permit Renewals Project stage: Request ML1104901652011-02-28028 February 2011 02/15/2011 Summary of Telephone Conference Call with the USNRC and NextEra Energy Seabrook, LLC, to Clarify the Responses to the RAIs Pertaining to the SAMA Review of the Seabrook Station License Renewal Application Project stage: RAI ML1105603622011-03-0101 March 2011 2/3/11 Summary of Telephone Conference Calls Held Between the USNRC and Nextera Energy Seabrook, LLC, to Clarify Information Pertaining to the Review of the Seabrook Station License Renewal Application Project stage: Approval ML1101001132011-03-0101 March 2011 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by Nextera Energy Seabrook, LLC for Renewal of the Operating License for Seabrook Station Project stage: Approval ML1105906382011-03-0404 March 2011 Schedule Revision and Request for Additional Information for the Review of the Seabrook Station License Renewal Application Environmental Review Project stage: RAI SBK-L-11044, Response to Request for Additional Information Regarding License Renewal Environmental Report2011-03-16016 March 2011 Response to Request for Additional Information Regarding License Renewal Environmental Report Project stage: Response to RAI 2010-08-10
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Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule 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-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 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 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23011A3082023-01-11011 January 2023 Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074) ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22228A0552022-08-15015 August 2022 Request for Additional Information Steam Generator Tube Inspection Report Review ML22153A4152022-05-31031 May 2022 Request for Additional Information Re 120V Inverter LAR from TS Branch - Final ML22062B6642022-02-0707 February 2022 Request for Additional Information 120V Inverter LAR from the Electrical Branch ML22063A0002022-01-25025 January 2022 Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR ML21245A4382021-10-0505 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise 120-Volt AC Vital Instrument Panel Technical Specification Requirements ML21097A2512021-04-0707 April 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Report Review for RFO 20 (EPID L-2020-LRO-0066) (Email) ML21054A0482021-02-23023 February 2021 Request for Additional Information Regarding Heat Flux Hot Channel Requirement Amendment Request ML20343A0942020-12-0303 December 2020 Request for Additional Information Regarding Seabrook (COVID-19) Part 73 Force-on-Force Exemption Request (L-2020-LLE-0219) ML20258A1502020-09-14014 September 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding One-Time Change to the AC Sources Operating TS ML20204A5422020-07-21021 July 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding Degraded Voltage Time Delay Setpoint ML20167A1842020-06-11011 June 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding TSTF-411 and TSTF-418 (L-2019-LLA-0237) ML20114E1592020-04-23023 April 2020 Email and Request for Additional Information Related to Seabrook License Amendment Request to Degraded Voltage Time Delay Setpoint (L-2020-LLA-0012) ML19296D9122019-10-23023 October 2019 NRR E-mail Capture - Request for Additional Information Related to Seabrook Inverter Amendment (L-2019-LLA-0216) ML18163A0352018-06-11011 June 2018 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML18121A3992018-05-0101 May 2018 NRR E-mail Capture - Request for Additional Information Regarding ASR Amendment Request ML18113A5292018-04-18018 April 2018 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18026A8792018-01-29029 January 2018 Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application Docket No. 05-443 ML17332A3412017-11-29029 November 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption ML17261B2172017-10-11011 October 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17276B7572017-10-0202 October 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17214A0852017-08-0404 August 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction ML17201Q1072017-07-18018 July 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17139B8352017-05-24024 May 2017 Final Request for Additional Information Regarding Seabrook License Renewal Application - Set 26 ML17150A2862017-05-0505 May 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17088A6142017-03-29029 March 2017 Request for Additional Information for the Review of the Seabrook Station License Renewal Application 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 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 ML16337A0082016-12-0101 December 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment Seabrook Station, License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency ML16326A0372016-11-30030 November 2016 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16301A4282016-11-14014 November 2016 Requests for Additional Information for the Review of the License Renewal Application ML16319A4222016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment ML16319A4212016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to EAL License Amendment ML16230A1062016-10-0303 October 2016 Request for Additional Information Request to Extend Containment Leakage Test Frequency ML16230A5332016-09-22022 September 2016 Request for Additional Information Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML16258A0222016-09-19019 September 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Alkali-Silica Reaction ML16187A2032016-07-0808 July 2016 Requests For Additional Information For The Severe Accident Mitigation Alternatives (SAMA) Review Of The Seabrook Station License Renewal Application (TAC No. Me3959)- Enclosure ML15328A1392015-12-0404 December 2015 November 23, 2015, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning Requests for Additional Information Pertaining to the Seabrook Station ML15251A3332015-10-0202 October 2015 Request for Additional Information Related to the Review of the Seabrook Station, Unit 1, License Renewal Application-SET 25 ML15224A5662015-08-28028 August 2015 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application-Set 24 ML15131A3382015-06-0505 June 2015 Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1,Radiation Monitoring for Plant Operations ML15043A2212015-02-24024 February 2015 Request for Additional Information for the Spring 2014 Steam Generator Tube Inspections 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 ML14358A0732014-12-24024 December 2014 Request for Additional Information for License Amendment Request 13-05. Fixed Incore Detector System Analysis Methodology ML14324A6372014-11-24024 November 2014 Request for Additional Information Regarding License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement 2023-06-22
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2012 Mr. Kevin Walsh Site Vice President clo Mr. Michael O'Keefe NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEABROOK STATION LICENSE RENEWAL APPLICATION ENVIRONMENTAL REVIEW - SAMA REVIEW (TAC NO. ME3959)
Dear Mr. Walsh:
By letter dated May 25, 2010, NextEra Energy Seabrook, LLC (NextEra) submitted an application and associated environmental report pursuant to Title 10 of the Code of Federal Regulations 10 CFR Part 51 and 10 CFR Part 54, to renew Operating License NPF-86 for Seabrook Station Unit 1 (Seabrook). In August 2011, the U.S. Nuclear Regulatory Commission (NRC or the staff) issued its draft plant-specific Supplement 46 to NUREG-1437, "Generic Environmental Impact Statement for License Renewal of Nuclear Plants" (SEIS), regarding the environmental impacts of renewing the Seabrook operating license for an additional 20 years.
Subsequent to the issuance of the draft SEIS, by letter dated March 19, 2012, NextEra submitted a supplement to its environmental report that identified changes that were made to the severe accident mitigation alternatives analysis (SAMA) related to the Seabrook license renewal application. The staff is reviewing the information contained in the supplement, and has identified, in the enclosure, areas where additional information is needed to complete the SAMA review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. Rick Cliche of your staff and a mutually agreeable date for the response is within 60 days from the date of this letter. If you have any questions, please contact me at 301-415-6459 or bye-mail at michael.wentzel@nrc.gov.
Sincerely, 1uJ{j~-
Michael wentz:~, Qect Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
As stated cc w/encl: Listserv
Request for Additional Information Regarding the Analysis of Severe Accident Mitigation Alternatives For the Seabrook Station License Renewal Review
- 1) Please provide the following information regarding the Level 1 Probabilistic Risk Assessment (PRA) used for the Severe Accident Mitigation Alternatives (SAMA) analysis:
- a. The Initiating Event Contribution to core damage frequency (CDF) Table in Section 3.1.1 of the Supplement presents initiating event contributors down to 2.5 percent of the total combined (i.e., internal and external) CDF. Please provide initiating event contributors down to 1.0 percent of the total CDF. If this addition includes contributors that did not previously appear, other than for the new flooding analysis, please discuss their new presence.
- b. Section 3.1 states on pages 4-5 that an installation of a flow orifice in fire protection piping in the control building is credited in the SB2011 probabilistic risk assessment (PRA) model update and is undergoing final acceptance testing. Please clarify when this design change will be implemented and whether it has passed final acceptance testing. In addition please verify that the as-built design change supports the PRA SAMA assumptions.
- c. The CDF for Station Blackout (SBO) and Anticipated Transient Without Scram (ATWS) is not presented, and it is not clear whether these values have changed from the original 2009 submittal. Please provide CDF values for SBO and A TWS.
- d. Previously, the contribution from internal events and internal floods together was 1.1 E-5/yr. This has dropped to 7.1 E-6/yr (see p. 16 of 96). The severe weather contribution, which is not insignificant at 10.0%, was not previously provided. Please explain all these differences, at least qualitatively.
- e. Among the basic event contributors to CDF and large early release frequency (LERF)
(see pp. 17 and 19 of 96) are several that differ from those in the January 13, 2011, RAI response. Please explain the increase in the RRW values for HH.XOEFW1.FA, HH.xIONES3.FA, and HH.OTSI3.FA and decrease in RRW value for FWP37A.FR for the LERF importance listing. Also, explain the basic events removed from and added to the LERF and CDF listings.
- 2) Please provide the following information relative to the Level 2 analysis:
- a. The discussion for source term group Small/Early Containment Penetration Failure to Isolate and Large/Late Containment Basemat Failure (SELL) identifies that SELL uses the source term from release category LL5a and frequency from release category SELL5a. The Table on page 6 identifies that LL5a is a contributor to source term group LL5. The discussion for LL5 identifies that MAAP Case #1 06f was used to provide a representative source term while the discussion for SELL identifies that MAAP Case
- 106g was used for this source group. Please clarify this apparent discrepancy.
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- b. The dose risk and Off-site Economic Cost Risk (OECR) results are different for the SB2006 and SB2011 PRA model results. The reason for these differences is not clear in every case. Using Table F.3.2.1-1 and requests for additional information (RAls) 2g and 4a associated with the SB2006 environmental report (ER), and release category results from the SB2011 submittal, please discuss the modeling basis that caused the following observations:
- i. LE1 - The CDF for this release category decreased from 1.1 E-7/yr to 5.2E-B/yr, and the SB2011 release fractions for the noble gases, iodine (I) and cesium (Cs),
are significantly delayed compared to their timing in the SB2006 model.
ii. LE2 - The CDF for this release category increased from 4.0E-9/yr to 1.BE-B/yr.
The SB2011 noble gas release fraction is similar to the SB2006 model, but the I and Cs release fractions are reduced by half.
iii. SE3 - The dose risk and OECR for this release category decreased by a factor of about three. The new SELL source term group appears to be a sub-part of the original small early containment isolation failure source term group (i.e., SE3).
- c. The dose risk and OECR results for release category LL5 changed significantly between SB2006 and SB2011 (greater than a factor of 100). The text on page 33 indicates that the increase in SAMA case "MAB" is due to higher release category source terms (apparently referring to LL5). The CDF for LL5 increased from 3.2E-7/yr to 3.1 E-6/yr, the SB2011 noble gas release fraction is similar to the SB2006 model, however the I and Cs release fractions are larger, and the release timing is significantly earlier. Please discuss the modeling basis that caused these changes.
- d. Please provide a general explanation of the differences in the release start times and durations from MAAP presented in the Table on page 12 from the release start times and durations presented in the Tables on pages 20-26 for MACCS. For example, for LE1, on page 12 the first puff release starts at 3.2 hr (-11,520 s) and the second puff starts at 39.3 hr (-141 ,BOO s). However, on page 20 the first plume starts at 932B s
(-2.6 hr) and the fourth plume starts at 172,BOO s (4B hr).
- 3) Please provide the following with regard to the SAMA identification and screening process:
- a. Two Tables in Section 3.1.1, Top 15 Basic Events Contributing to CDF and Top 15 Basic Events Contributing to LERF, provide the Risk Reduction Worth (RRW) for CDF and LERF down to a value of 1.02. IN Section 4.1 the Top 15 Basic Events Contributing to CDF, LERF, and release category (RC) contributing to 90 percent of the Public Risk provides the top 15 basic events for each of the following: CDF, LERF (which includes LE1, LE2, LE3, and LE4), and RCs LL-5, SE-3, and SELL. The RRW values for basic events importance to LL-5, SE-3, and SELL are not provided. In an RAI response dated January 13, 2011, the top 15 basic events were provided along with their corresponding RRW values for the risk dominant (i.e., contributing to 90 percent of the population dose) release categories (Le., SE3, LL3, LE1, SE1, and LL4). From RAI responses it could be determined that the maximum benefit that might be calculated from eliminating the 15th most important basic event resulted in benefits less than a simple hardware implementation cost of (i.e., $100K). Given the changes in release frequencies, such as the 10 fold increase in LL5, it is not clear whether all important basic events are ENCLOSURE
-3 identified as part of the 45 basic events presented in the Section 4.1 table. Please provide the RRWs for basic events contributing to LL-5, SE-3, and SELL down to a minimum RRW value that would ensure the maximum possible benefit would exceed the cost of a simple hardware or administrative change (-$1 OOK). If this requires addressing further basic events, please include their evaluation in Table 2 of Section 4.3.
- b. Table 2 of Section 4.3 provides the benefit of SAMAs specifically devised for reducing the risk associated with each of the top 16 initiating events contributing to CDF and the top 15 initiating contributing to LERF. The RRW values for these initiating events are not provided, and because they are not provided it is not clear if all important initiators against CDF and LERF are addressed by SAMA evaluation. Please provide RRWs values for initiating events against CDF and LERF. Provide importance analysis listing down to a minimum RRW value that would ensure that the maximum possible benefit would exceed the cost of a simple hardware or administrative change (-$100K). If this requires addressing more than the 16 initiating events already considered against CDF and the 15 initiating events already considered against LERF please include their evaluation in Table 2 of Section 4.3.
- c. Step (b) in the general approach to the reassessment (Section 2.0) does not list at least three criteria by which SAMA candidates were previously eliminated: (1) being combined with another similar SAMA, (2) costing more than the MAS, and (3) being related to a non-risk significant system. Please provide additional information describing how these criteria were considered in the re-assessment. (Note that this RAI also applies to step 2 in Section 4.1 [see. p. 28 of 96].)
- 4) Please provide the following with regard to the Phase II cost-benefit evaluations:
- a. In Section 4.2, on p. 34 of 96, it is stated that "[t]he sensitivity of the updated SAMA results to variations in other Level 3 parameters is expected to be consistent with previous sensitivity results." Please provide discussion comparing the updated results to the previous results confirming this expectation.
- b. In Section 4.2, on p. 35 of 96, itis stated that "[n]o new potentially cost-beneficial SAMAs were [sic] identified as a result of the 3% and 8.5% sensitivity calculations." Please clarify if this is relative to the original analysis (submittal plus RAI responses) or to the re analysis provided here for cost-beneficial SAMAs.
- c. Section 4.2 provides the new Maximum Averted Senefit (MAS) (Le., $3.05M) using the SSPSS-2011 PRA model. Also please provide the Averted Public Exposure (APE) costs, Averted Off-site Property Damage Costs (AOC), Averted Occupational Exposure (AOE) costs, and Averted Onsite Costs (AOC).
- d. In Table 1 of Section 4.3, neither the risk reduction values nor PRA modeling assurnptions for SAMA case MAS are provided. The evaluation for SAMA 77 incorrectly states that "Cost to engineer and implement installation of large passive air cooling system is far in excess of the attainable benefit". The original SAMA evaluation submittal estimated the cost of implementing this SAMA to be >$3M. Please provide the risk reduction values and PRA modeling assumptions for SAMA case MAS. Also, please provide justification of the cost of SAMA 77 and explain why it was necessary to increase this cost estimate.
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- e. Table 1 of Section 4.3 presents revised SAMA case CONTX1 which is defined to eliminate alternating current (AC) and direct current (DC) power and Primary Component Cooling Water (PCCW) support system failures for one division of Containment Building Spray (CBS). The evaluation for this SAMA case explains that this case more realistically represents the potential risk reduction benefit than the case it replaced (Le.,
CONT01 - Installation of an independent division of containment spray). It is not clear that the PRA assumption for this case (CONTX1), which consists of eliminating support system failures, bounds the SAMAs represented by this case (Le., #91, #94, #99, #102, and #107). In light of the potentially high cost benefit (the current cost benefit with uncertainty and the seismic multiplier is >$5.7M), please provide justification for why this case is representative of each SAMA grouped under it and clarify whether a less restrictive or different case may be more appropriate. If a less restrictive or different case may be more appropriate please provide the corresponding evaluations.
- f. In Table 1 of Section 4.3, the expected cost of SAMA 162 (Increase the capacity margin of the condensate storage tank (CST>> is >$2.5M. In the original submittal the expected cost of this SAMA was presented as >$100K. The evaluation of this SAMA in the supplement states that the "Cost of expanding capacity of the CST is based on project scope of installing a new (larger) safety grade CST, which is judged necessary to achieve full benefit." In light of the fact that the new cost benefit with uncertainty and the seismic multiplier is $171 K, please explain the basis for the earlier cost estimate and why it was necessary to increase this cost estimate by a factor of 25.
- g. In Table 1 of Section 4.3, the expected cost of SAMA 189 (Modify or analyze supplemental emergency power supply (SEPS) capability; 1 of 2 SEPS for loss of off site power (LOSP) non-safety injection (SI) loads, 2 of 2 LOSP Slloads) is >$2M. In the original submittal the expected cost of this SAMA was presented as >$300K. The SAMA appears that it could primarily be an analytical task. In light of this and the fact that the new cost benefit with uncertainty and the seismic multiplier is $311 K, please explain why it was necessary to increase this cost estimate by a factor of 7.
- h. In Table 2 of Section 4.3, the cost benefit for SAMA case OHSBO (for BE #5) is presented as >$1M in the "Expected SAMA cost" column, yet the discussion in the "Evaluation" column states that the cost was estimated to be $1.5M. Please clarify this apparent discrepancy.
- i. In Table 2 of Section 4.3, the evaluation for BE #34 states that the PRA case "conservatively assumes that elimination of Bus E5 and E6 random failures that could cause an initiating event. ... and/or fail the associated power division during mission time". Please clarify whether the PRA assumptions for this modeling case (i.e.,
SWGE561) include elimination of initiators, basic events or both.
- j. In Table 2 of Section 4.3, the event description for BE #38 refers to operator actions after loss of coolant accident (LOCA) and steam generator tube rupture (SGTR), but the evaluation refers to actions after a small LOCA (SLOCA) and interfacing system LOCA (ISLOCA). Please clarify this apparent discrepancy.
- k. In Table 2 of Section 4.3, the entries for IE #8 and #9 appear to be duplicates. Please clarify.
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- 5 I. In Table 2 of Section 4.3, the cost benefit analyses provided for IE #16 is a hardware installation to improve Component Cooling Water (CCW) reliability. In the evaluation for IE #16 on page 93 the associated SAMA case (Le., CCTE1) is not identified as a cost beneficial SAMA. Yet, CCTE1 is identified as cost beneficial in Table 1 on page 65.
Please clarify this apparent discrepancy.
- m. In Table 2 of Section 4.3, cost benefit analyses are provided for IE #23, #24, #25, #26, and #27, which are seismic initiators of different levels, (0.7g, 1.0g, 1.4g, 1.8g, and 2.5g) that lead to A TWS events (SAMA case NOATWS). No description of the associated SAMA is provided nor is the basis for the presented cost estimate (Le., >$500K). Table 2 shows that IE #28, which is an A TWS event with loss of Main Feedwater, is also grouped into this SAMA case. It is not clear why this initiating event (Le., IE#28) can be grouped as part of a seismic upgrade related SAMA case. Please provide the SAMA description and basis for the cost estimate for these six initiator cases.
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ML12180A355 OFFICE LA:RPB1 :DLR PM:RPB2:DLR OGC BC:DLRRPB2 D:DLRRPB2 I NAME YEdmonds MWentzel MSpencer DWrona MWentzel lEATE 7/12/12 7/12/12 7/12/12 7/16/12 7/16/12 Letter to K. Walsh from M. Wentzel dated July 16, 2012
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEABROOK STATION LICENSE RENEWAL APPLICATION ENVIRONMENTAL REVIEW - SAMA REVIEW (TAC NO. ME3959)
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PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDraApla Resource SeabrookPEm Resource ACunnan MWentzel DWrona DMorey JLamb RGal1ucci JParilio TTate DMclntyre, OPA EDacus,OCA MSpencer,OGC WRaymond, RI JDeBoer, RI DTifft, RI NMcNamara, RI NSheehan, RI DScrenci, RI ABurritt, RI