|
|
Line 22: |
Line 22: |
|
| |
|
| ==References:== | | ==References:== |
| : 1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010. (Accession Number ML101590099) | | : 1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010. (Accession Number ML101590099) |
| : 2. NRC Letter, Requests for Additional Information for the Severe Accident Mitigation Alternatives ( S AM A) Review of the Seabrook Station License Renewal Application (TAC No. ME3959), July 8, 2016, (Accession Number ML16187A204) | | : 2. NRC Letter, Requests for Additional Information for the Severe Accident Mitigation Alternatives ( S AM A) Review of the Seabrook Station License Renewal Application (TAC No. ME3959), July 8, 2016, (Accession Number ML16187A204) |
| : 3. Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 (Accession Number ML16125Al50) | | : 3. Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 (Accession Number ML16125Al50) |
| In Reference 1, NextEra Energy Seabrook, LLC (NextEra) 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 staff requested additional information to support addressing the Commission Memorandum and Order (CLI-16-07) which directed the NRC staff to supplement the SAMA analysis performed for the Indian Point Units 2 and 3 LRA with sensitivity analyses for two factors used in the SAMA analysis (Reference 3). The NextEra Seabrook response to the RAI is provided in the enclosure to this letter. The RAI response includes the results of a sensitivity analysis for the same two input parameters addressed by the Commission in CLI-16-07. The sensitivity analysis demonstrates that the SAMA analysis previously submitted for Seabrook Station remains bounding. NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 | | In Reference 1, NextEra Energy Seabrook, LLC (NextEra) 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 staff requested additional information to support addressing the Commission Memorandum and Order (CLI-16-07) which directed the NRC staff to supplement the SAMA analysis performed for the Indian Point Units 2 and 3 LRA with sensitivity analyses for two factors used in the SAMA analysis (Reference 3). The NextEra Seabrook response to the RAI is provided in the enclosure to this letter. The RAI response includes the results of a sensitivity analysis for the same two input parameters addressed by the Commission in CLI-16-07. The sensitivity analysis demonstrates that the SAMA analysis previously submitted for Seabrook Station remains bounding. NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 |
Line 46: |
Line 46: |
| Specifically, the Commission held that documentation was lacking for two inputs (TIMDEC and CDNFRM) used in the MACCS computer analyses, and that uncertainties in those input values could potentially affect the SAMA analysis cost-benefit conclusions. | | Specifically, the Commission held that documentation was lacking for two inputs (TIMDEC and CDNFRM) used in the MACCS computer analyses, and that uncertainties in those input values could potentially affect the SAMA analysis cost-benefit conclusions. |
| The Commission therefore directed the Staff to perform additional sensitivity analyses. | | The Commission therefore directed the Staff to perform additional sensitivity analyses. |
| The two inputs (TIMDEC and CDNFRM), are commonly used in the SAMA analyses performed for license renewal applications (LRAs ). These two input values were generally based on the values provided in NUREG-1150, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants" and NUREG/CR-3673, "Economic Risks of Nuclear Power Reactor Accidents." The TIMDEC input value defines the time required for completing decontamination to a specified degree. The CDNFRM input parameter defines the cost (on a per person basis) of decontaminating non-farmland by a specified decontamination factor. The CDNFRM values used in NUREG-1150 | | The two inputs (TIMDEC and CDNFRM), are commonly used in the SAMA analyses performed for license renewal applications (LRAs ). These two input values were generally based on the values provided in NUREG-1150, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants" and NUREG/CR-3673, "Economic Risks of Nuclear Power Reactor Accidents." The TIMDEC input value defines the time required for completing decontamination to a specified degree. The CDNFRM input parameter defines the cost (on a per person basis) of decontaminating non-farmland by a specified decontamination factor. The CDNFRM values used in NUREG-1150 |
| ($3,000/personfor decontamination factor of 3 and $8,000/person for decontamination factor of 15) stem from decontamination cost estimates provided in NUREG/CR-3673, the same 1984 economic risk study referenced in support of the decontamination time inputs. These decontamination cost inputs are commonly escalated to account for inflation. | | ($3,000/personfor decontamination factor of 3 and $8,000/person for decontamination factor of 15) stem from decontamination cost estimates provided in NUREG/CR-3673, the same 1984 economic risk study referenced in support of the decontamination time inputs. These decontamination cost inputs are commonly escalated to account for inflation. |
| REQUEST FOR ADDITIONAL INFORMATION: | | REQUEST FOR ADDITIONAL INFORMATION: |
Letter Sequence Response to RAI |
---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement
|
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
[Table View] |
|
---|
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
[Table view] |
Text
. \. U.S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station NEXTera SEABROOK September 6, 2016 10 CFR 54 SBK-L-16134 Docket No. 50-443 Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application
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 Letter, Requests for Additional Information for the Severe Accident Mitigation Alternatives ( S AM A) Review of the Seabrook Station License Renewal Application (TAC No. ME3959), July 8, 2016, (Accession Number ML16187A204)
- 3. Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 (Accession Number ML16125Al50)
In Reference 1, NextEra Energy Seabrook, LLC (NextEra) 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 staff requested additional information to support addressing the Commission Memorandum and Order (CLI-16-07) which directed the NRC staff to supplement the SAMA analysis performed for the Indian Point Units 2 and 3 LRA with sensitivity analyses for two factors used in the SAMA analysis (Reference 3). The NextEra Seabrook response to the RAI is provided in the enclosure to this letter. The RAI response includes the results of a sensitivity analysis for the same two input parameters addressed by the Commission in CLI-16-07. The sensitivity analysis demonstrates that the SAMA analysis previously submitted for Seabrook Station remains bounding. NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
' ' United States Nuclear Regulatory Commission
'SBK-L-16134 I Page 2 No new commitments are being made in this submittal.
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. Ken Browne, Licensing Manager, at (603) 773-7932.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September
___fo__, 2016 Sincerely,
Enclosure:
Response to RAI Related to Severe Accident Mitigation Alternatives cc: D. H. Dorman J.C. Poole P. C. Cataldo T. M. Tran L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal NRC Project Manager, License Renewal Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
. ,, U.S. Nuclear Regulatory Commission
/Enclosure I Page 1 Enclosure to SBK-L-16134 NextEra Energy Seabrook Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application
. \ U.S. Nuclear Regulatory Commission
'SBK-L-16134
/Enclosure I Page 2 NRC RAI for Licensees regarding CLI-16-07 BACKGROUND:
On May 4, 2016, the Commission issued a Memorandum and Order (CLI-16-07) in the Indian Point license renewal proceeding, in which it directed the Staff to supplement the Indian Point Severe Accident Mitigation Alternatives (SAMA) analysis with sensitivity analyses.
Specifically, the Commission held that documentation was lacking for two inputs (TIMDEC and CDNFRM) used in the MACCS computer analyses, and that uncertainties in those input values could potentially affect the SAMA analysis cost-benefit conclusions.
The Commission therefore directed the Staff to perform additional sensitivity analyses.
The two inputs (TIMDEC and CDNFRM), are commonly used in the SAMA analyses performed for license renewal applications (LRAs ). These two input values were generally based on the values provided in NUREG-1150, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants" and NUREG/CR-3673, "Economic Risks of Nuclear Power Reactor Accidents." The TIMDEC input value defines the time required for completing decontamination to a specified degree. The CDNFRM input parameter defines the cost (on a per person basis) of decontaminating non-farmland by a specified decontamination factor. The CDNFRM values used in NUREG-1150
($3,000/personfor decontamination factor of 3 and $8,000/person for decontamination factor of 15) stem from decontamination cost estimates provided in NUREG/CR-3673, the same 1984 economic risk study referenced in support of the decontamination time inputs. These decontamination cost inputs are commonly escalated to account for inflation.
REQUEST FOR ADDITIONAL INFORMATION:
The NRC Staff believes the Commission's decision in CLI-16-07 may be applicable to the SAMA analysis performed for Seabrook Station, Unit 1 (Seabrook), inasmuch as that analysis may have also relied upon the NUREG-1150 values for TIMDEC and CDNFRM. We therefore request that NextEra Energy Seabrook, LLC (NextEra), either justify why CLI-16-07 does not apply to the SAMA analysis performed for Seabrook or supplement the SAMA analysis with sensitivity analyses for the CDNFRM and TIMDEC values. NextEra is requested to review the input values specified_in CLI-16-07 for the Indian Point LRA, and (1) to apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000 for the CDNFRM values for the decontamination factor of 15) or, in the alternative, (2) to explain, with sufficient justification, its rationale for choosing any other value(s) for its sensitivity analyses.
In any event, NextEra should execute sensitivity analyses for the release categories modeled that exceed 10 15 Becquerels ofCs-137 released.
NextEra is requested to evaluate how these sensitivity analyses may affect its identification of potentially cost-beneficial SAMAs. Finally, upon completing its sensitivity analysis, NextEra is requested to submit the spreadsheet (or equivalent table if another method is used) that conveys the population dose and off-site economic cost for each release category and integrates the results into a Population Dose Risk and an Offsite Economic Cost Risk for Seabrook.
. \. ' U.S. Nuclear Regulatory Commission
'SBK-L-16134
/Enclosure I Page 3 NextEra Seabrook Response
Background:
As discussed in the RAI, the NRC Commissioners issued a Memorandum and Order (CLI-16-07) in the matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) on May 4, 2016 (Enclosure Reference 1-1 ). The Commissioners directed the NRC staff to supplement Indian Point's SAMA analysis with a sensitivity analysis using values of 365 days for the TIMDEC input parameter and $100,000/person for heavy decontamination for the CDNFRM input parameter in the MACCS2 (MELCOR Accident Consequence Code) code for at least the four most severe accident categories modeled. The RAI issued to NextEra Energy Seabrook Station requests that Seabrook apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000/person for the CDNFRM values for the decontamination factor of 15) for the release categories modeled that exceed 10 15 Becquerels of Cs-137 released or, in the alternative, explain the rationale for choosing other values for the sensitivity analyses.
NextEra Energy has performed a SAMA sensitivity analysis for Seabrook Station using the maximum input parameter values specified by the Commission in CLl-16-07 and by the NRC Staff in the RAI. The results of that analysis are described and summarized below. Decontamination Sensitivity Analysis A sensitivity analysis to determine the Modified Maximum Averted Cost Risk (MMACR) using the highest values allowed in MACCS2 for inputs TIMDEC and CDNFRM, 365 days and $100,000/person, respectively, for the decontamination factor of 15 (heavy decontamination), was performed as specified in CLI-16-07 and in the RAI. All other inputs into the MACCS2 code were unchanged.
The evaluation used the higher TIMDEC and CDNFRM input parameter values in the same sensitivity analysis, so that the effects of increasing both values are evaluated concurrently.
The RAI indicates that the severe accident categories that exceed 10 15 Becquerels of Cs-13 7 released should be considered.
Accident releases from Seabrook are modeled via 13 release categories (RC). 10 of the 13 accident release categories exceed the 10 15 Becquerels for Cs-137, all of the release categories except SEl, INTACTl and INTACT2. However, as a conservative approach, all of Seabrook's release categories are included in this sensitivity analysis.
This includes the following release categories:
LEl -Large/Early Cont. Bypass-SG Tube Rupture LE2 -Large/Early Cont. Bypass -ISLOCA LE3 -Large/Early Cont. Penetration Failure to Isolate LE4 -Large Cont. Basemat Failure with Delayed Evacuation SEl -Small/Early Cont. Bypass-SG Tube Rupture w/ Scrubbed Release SE2 -Small/Early Cont. Bypass -ISLOCA w/ Scrubbed Release SE3 -Small/Early Cont. Penetration Failure to Isolate LL3 -Large/Late Cont. Venting LL4 -Large/Late Cont. Overpressure Failure LL5 -Large/Late Cont. Basemat Failure
' . U.S. Nuclear Regulatory Commission
'SBK-L-16134*/Enclosure I Page 4 SELL -Small/Early Cont. Pen. Failure to Isolate & Large/Late Cont. Basemat Failure INTACT! -Nominal Cont. Leakage (mapped to INTACT) INTACT2 -Excessive Cont. Leakage (mapped to INTACT) INTACT-Weighted summation ofINTACTl and INTACT2 After determining the revised population dose and economic costs using the maximum values for CDNFRM and TIMDEC for the above release categories, a Maximum Averted Cost Risk (MACR) was calculated for both the 7% (base) and 3% (sensitivity) discount rates as done in the Seabrook SAMA analysis.
In addition, the MACR is increased by a factor of 2.1 to account for the potential risk increase due to seismic hazards. The seismic multiplier was derived and justified as discussed on page 29 of 96 in Enclosure Reference 1-2. The seismic-adjusted MACR is referred to as the "modified" Maximum Averted Cost Risk (MMACR). Note that in the previous Seabrook SAMA documentation, MMACR was referred to as the Maximum Averted (Attainable)
Benefit (MAB), which provided the same measure of benefit. The MMACR calculated in this RAI sensitivity analysis is then compared to the 95th percentile MMACR determined in the Seabrook SAMA analysis.
The 95th percentile MMACR is obtained by multiplying the MMACR by a factor of2.35 to account for the 95th percentile of the consequence as discussed on page 35of96 in Enclosure Reference 1-2. RAI Sensitivity Results I Comparison Table 1 presents the Level 3 base case results of Public Dose and Economic Risk from the previous Seabrook SAMA evaluation, page 27of96 in Enclosure Reference 1-2. The results of this RAI sensitivity analysis are presented in Tables 2 and 3. Table 2 provides the Population Dose Risk and Economic Cost Risk for each release category.
Table 3 compares the Modified Maximum Averted Cost Risk (MMACR) results calculated for both the SAMA base case and the RAI sensitivity case. The results show that the MMACR for the RAI sensitivity case, which used CDNFRM and TIMDEC set to their maximum allowable values for heavy decontamination, is $9,607,670/year for a 7% discount rate. This MMACR is bounded by the 95th percentile of the MMACR in the Seabrook SAMA evaluation which was derived as 2.35 x $6,401,871/year
= $15.04M/year.
Likewise, the RAI sensitivity analysis MMACR calculated with maximum values for CDNFRM and TIMDEC using a 3% discount rate is $13.67M, which is also bounded by the 95th percentile base case of $15.04M/yr.
. \ U.S. Nuclear Regulatory Commission -SBK-L-16134 /Enclosure I Page 5 Table 1 Seabrook SAMA Base Case Level 3 Results (*) Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REI\ll) ($) (events/yr) (person ($/yr) REM/y r) LE-1 1.26E+07 5.60E+ I 0 5.19E-08 6.54 E-OI 2.91E+03 LE-2 4.27E+07 7.14E+l0 l.8 lE-08 7.73E-Ol l.29E+0 3 LE-3 2.41E+07 6.80 E+l 0 8.61E-10 2.08E-02 5.85E+Ol LE-4 l.1 l E+07 4.91E+l0 2.11 E-08 2.34E-Ol l .0 4E+03 SE-1 2.43E+05 3.27£+08 5.08E-07 1.23£-01 l.66E+02 SE-2 8.60E+06 3.09E+IO 2.79£-08 2.40£-01 8.62E+02 SE-3 l.36E+06 2.67£+09 9.97£-07 1.36£+00 2.66E+03 LL-3 3.63E+06 9.05£+09 1.75£-07 6.35£-01 l.5 8 E+03 LL-4 7.27E+06 3.lO E+lO 5.79E-08 4.21E-01 I .79E+0 3 LL-5 1.03£+07 5.24£+10 3.IOE-06 3.19E+Ol 1.6 2£+05 SELL l .48E+07 6.53E+10 9.84 E-08 l.46 E+OO 6.43E+03 INTACT 2.77E+03 2.18£+03 7.14£-06 1.98£-02 l .56E-02 Totals 1.37E+08 4.36E+ll 1.22E-05 3.79E+Ol 1.81E+05 (*) T a ble 1 i s r eproduced from table of relea se c a tegor y public dose and economic ri s k re s ults -Level 3 Mod e l provided in letter SBK-L-1 2053 (Enc l osure Reference 1-2), pa g e 27 of96. Table 2 Seabrook SAMA RAI Sensitivity Level 3 Results Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REM) ($) (events/y r) (person ($/y r) REM/y r) LE-1 l.24E+07 l.l!E+ll 5.19£-08 6.44E-01 5.76E+03 LE-2 4.29E+07 1.34E+ 11 1.81E-08 7.76 E-01 2.43E+03 LE-3 2.4 6E+07 l.39 E+ 11 8.6 1E-10 2.12E-02 l.2 0 E+02 LE-4 1.14E+07 9.89E+l0 2. l IE-08 2.4 lE-01 2.09 E+0 3 SE-1 2.4 7E+05 7.18 E+08 5.08E-07 1.25£-01 3.65E+02 SE-2 9.04E+06 6.69E+l0 2.79E-08 2.52E-Ol 1.87£+03 SE-3 l.35E+06 4.01E+09 9.97E-07 l.35 E+OO 4.00E+03 LL-3 3.68E+06 J.68 E+IO J.75E-07 6.44E-O 1 2.94E+03 LL-4 7.90E+06 6.41E+l0 5.79E-08 4.57E-Ol 3.71E+03 LL-5 9.64E+06 9.40£+10 3.l O E-06 2.99E+Ol 2.9J E+05 SELL 1.47E+07 l .26E+ 11 9.84£-08 1.45£+00 1.24£+04 INTACT 2.77E+03 2.18E+03 7.14£-06 l .98 E-02 1.5 6 E-02 Totals 1.38E+08 8.55E+ll 1.22E-05 3.59E+Ol 3.27E+05
.. U.S. Nuclear Regulatory Commission
'SBK-L-16134
/Enclosure I Pa ge 6 Table 3 Seabrook Modified Maximum Averted Cost Risk Results I Comparison Base Case Results RAI Sensitivity Results Description 7% Real 3% Discount 7% Real 3% Discount Discount Rate Rate Sensitivity Discount Rate Rate Sensitivity Averted Public Exposure Cost (APE) $815 , 072 $1 , 138 , 946 $771 , 886 $1,078,600 Averted Offsite Property Damage Cost $1,950,586
$2 , 725 , 665 $3 , 520 , 343 $4 , 919, 175 (AOC) Averted Occupational Exposure Cost (AOE) $4,642 $7,549 $4,642 $7 , 549 Averted Onsite Cost (AOC) $278,2 10 $506,062 $278 , 210 $506 , 062 Maximum Averted Cost Risk ($/yr) $3 , 048 , 510 $4 , 378 , 222 $4,575 , 081 $6,511,386 Seismic Hazard Multiplier 2.10 2.10 2.10 2.10 Modified Maximum Averted Cost Risk $6,401,871
$9 , 194 , 265 $9,607 , 670 $13 , 673 , 911 ($/yr) Uncertainty Factor ( 95th Percentile) 2.35 Total MMACR at 95 111 Percentile Uncertainty
$15.04M Distribution
==
Conclusion:==
As summarized in Table 3 , the sensitivity va lues for the Modified Maximum Averted Cost Risk (MMACR) are bounded b y the previous Seabrook SAMA MMACR, which accounted for the 95th percentile in averted cost risk. Additionally, the maximum increase in benefit of an individual SAMA candidate is bounded by the previous 95th percentile case. The maximum increased value of an individual SAMA candidate could be no greater than the largest ratio of the population dose risk or economic risk of the decontamination sensitivity case to the population dose risk or economic risk in the previous Seabrook SAMA case (Table 1) for all of the modeled release categories. The maximum increase ratio is less than the factor of 2.35 used in Seabrook's SAMA evaluation to judge each individual SAMA candidate against the benefit , which considered the benefit at the 95 1 h percentile.
Therefore, the results of the evaluation of potential SAMA candidates previously provided in the SAMA analysis bounds the results of the RAI sensitivity analysis.
While the use of the higher RAI decontamination input parameters results in an increase in the MMACR, the RAI sensitivity analysis shows that the results are less than Seabrook's base SAMA MMACR, which considered the MMACR at the 95th percentile.
Based on the above , the RAI sensitivity results do not present any new and significant information that could necessitate supplementation of the Final Supplemental Environmental Impact Statement for the Seabrook Station licen se renewal.
- , ' U.S. Nuclear Regulatory Commission
/Enclosure I Pag e 7 Enclosure References
- 1-1 Commissioner Memorandum and Order , CLI-16-07 , "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 1-2 NextEra Energy Seabrook Station Letter to NRC , " Seabrook Station Supplement 2 to Severe Accident Mitigation Alternati ves Analysis" SBK-L-12053 , dated March 19 , 2012 (Accession Number ML12080Al37)