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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 October 17,2012 Mr. Bruce Skud No More Fukushimas 14 Olive Street Newburyport, MA 01950 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 17,2012 Mr. Bruce Skud No More Fukushimas 14 Olive Street Newburyport, MA 01950 |
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| ==Dear Mr. Skud:== | | ==Dear Mr. Skud:== |
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| On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to the letter of August 28, 2012, from you and Ms. Joanna Hammond to Chairman Macfarlane expressing concerns about the license renewal process for the Seabrook Station. In your letter, you specifically discussed issues with concrete degradation in safety-related structures, projections about plant flood levels, and a recent emergency preparedness exercise. | | On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to the letter of August 28, 2012, from you and Ms. Joanna Hammond to Chairman Macfarlane expressing concerns about the license renewal process for the Seabrook Station. In your letter, you specifically discussed issues with concrete degradation in safety-related structures, projections about plant flood levels, and a recent emergency preparedness exercise. |
| Be assured that the NRC is thoroughly evaluating the Seabrook Station license renewal application, including the observed concrete degradation. | | Be assured that the NRC is thoroughly evaluating the Seabrook Station license renewal application, including the observed concrete degradation. In addition, inspectors from the NRC's Region I office have been conducting inspections and technical reviews to evaluate and assess this issue. |
| In addition, inspectors from the NRC's Region I office have been conducting inspections and technical reviews to evaluate and assess this issue. Regarding your concerns about the current design-basis flood level calculations and the licensee's performance during a recent emergency preparedness exercise, please note that these issues are not part of the NRC's review of a license renewal application. | | Regarding your concerns about the current design-basis flood level calculations and the licensee's performance during a recent emergency preparedness exercise, please note that these issues are not part of the NRC's review of a license renewal application. A license renewal review is not a re-review of the facility licensing basis; rather, it is focused on managing the age-related degradation of passive systems, structures, and components to ensure they will fulfill their safety-related functions, as specified in the current licensing basis. |
| A license renewal review is not a re-review of the facility licensing basis; rather, it is focused on managing the age-related degradation of passive systems, structures, and components to ensure they will fulfill their safety-related functions, as specified in the current licensing basis. The NRC has multiple processes to evaluate the adequacy of current plant operations and licensing bases. Should the NRC become aware at any time of information calling into question the continued safe operation of any nuclear power plant, including Seabrook Station, the NRC will take the appropriate actions as part of the agency's ongoing safety oversight, regardless of whether those plants have sought or are seeking a renewed license. With regard to the Seabrook Station license renewal application, no decision on whether a renewed license will be or will not be granted, has been made because the NRC's review is ongoing. Further, the applicant has not sufficiently described the actions and technical basis to adequately manage the long-term aging effects on concrete structures. | | The NRC has multiple processes to evaluate the adequacy of current plant operations and licensing bases. Should the NRC become aware at any time of information calling into question the continued safe operation of any nuclear power plant, including Seabrook Station, the NRC will take the appropriate actions as part of the agency's ongoing safety oversight, regardless of whether those plants have sought or are seeking a renewed license. |
| Until such information has been provided and found acceptable by the NRC, a renewed license cannot be issued to the Seabrook Station. | | With regard to the Seabrook Station license renewal application, no decision on whether a renewed license will be or will not be granted, has been made because the NRC's review is ongoing. Further, the applicant has not sufficiently described the actions and technical basis to adequately manage the long-term aging effects on concrete structures. Until such information has been provided and found acceptable by the NRC, a renewed license cannot be issued to the Seabrook Station. |
| B. Skud -Thank you for your interest in this matter. We intend to keep the public fully informed of our review and inspection results, as this matter continues forward in the license renewal review process. The NRC is committed to ensuring the continued safe operation of U.S. Nuclear Power Plants, including the Seabrook Station. ennis , Projects Branch Division of Licens Office of Nuclear Docket No. 50-443 cc: Listserv B. Skud Thank you for your interest in this matter. We intend to keep the public fully informed of our review and inspection results, as this matter continues forward in the license renewal review process. The NRC is committed to ensuring the continued safe operation of U.S. Nuclear Power Plants, including the Seabrook Station. Sincerely, IRA! Dennis Morey, Chief Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-443 cc: Listserv DISTRIBUTION: | | |
| G20120651/LTR-12-0476 HARDCOPY:
| | B. Skud - 2 Thank you for your interest in this matter. We intend to keep the public fully informed of our review and inspection results, as this matter continues forward in the license renewal review process. The NRC is committed to ensuring the continued safe operation of U.S. Nuclear Power Plants, including the Seabrook Station. |
| DLRRF EMAIL: PUBLIC DMorey RidsNrrDlr Resource PMilano RidsNrrDlrRpb1 Resource MWentzel RidsNrrDlrRarb Resource RAuluck RidsNrrDlrRapb Resource MMarshall RidsNrrDlrRasb Resource STurk,OGC RidsNrrDlrRerb Resource MSpencer, OGC RidsNrrDlrRsrg Resource JTrapp, RI RidsNrrDeEmcb Resource RConte, RI RidsEdoMailCenter Resource DScrenci, RI OPA RidsSecyMailCenter Resource NSheehan, RI OPA RidsRgn1 MailCenter Resource NMcNamara, RI RidsOgcMailCenter Resource SBurnell, OPA DMclntyre, OPA MHalter, RI ADAMS Accession Nos.: ML12279A291 (Pkg.); ML12244A548 ML12279A288(Response)
| | ennis , |
| *via OFFICE I PM:RPB1 :DLR LA:RPB1 :DLR* OGC (NLO) BC:RPB1 :DLR NAME PMilano YEdmonds MSmith DMorev DATE 10/10/12 10/10/12 10/12/12 10/17/12 OFFICIAL RECORD}} | | Projects Branch Division of Licens Office of Nuclear Docket No. 50-443 cc: Listserv |
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| | ML12279A291 (Pkg.); ML12244A548 (Incoming); |
| | ML12279A288(Response) *via email OFFICE I PM:RPB1 :DLR LA:RPB1 :DLR* OGC (NLO) BC:RPB1 :DLR NAME PMilano YEdmonds MSmith DMorev DATE 10/10/12 10/10/12 10/12/12 10/17/12}} |
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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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 17,2012 Mr. Bruce Skud No More Fukushimas 14 Olive Street Newburyport, MA 01950
Dear Mr. Skud:
On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to the letter of August 28, 2012, from you and Ms. Joanna Hammond to Chairman Macfarlane expressing concerns about the license renewal process for the Seabrook Station. In your letter, you specifically discussed issues with concrete degradation in safety-related structures, projections about plant flood levels, and a recent emergency preparedness exercise.
Be assured that the NRC is thoroughly evaluating the Seabrook Station license renewal application, including the observed concrete degradation. In addition, inspectors from the NRC's Region I office have been conducting inspections and technical reviews to evaluate and assess this issue.
Regarding your concerns about the current design-basis flood level calculations and the licensee's performance during a recent emergency preparedness exercise, please note that these issues are not part of the NRC's review of a license renewal application. A license renewal review is not a re-review of the facility licensing basis; rather, it is focused on managing the age-related degradation of passive systems, structures, and components to ensure they will fulfill their safety-related functions, as specified in the current licensing basis.
The NRC has multiple processes to evaluate the adequacy of current plant operations and licensing bases. Should the NRC become aware at any time of information calling into question the continued safe operation of any nuclear power plant, including Seabrook Station, the NRC will take the appropriate actions as part of the agency's ongoing safety oversight, regardless of whether those plants have sought or are seeking a renewed license.
With regard to the Seabrook Station license renewal application, no decision on whether a renewed license will be or will not be granted, has been made because the NRC's review is ongoing. Further, the applicant has not sufficiently described the actions and technical basis to adequately manage the long-term aging effects on concrete structures. Until such information has been provided and found acceptable by the NRC, a renewed license cannot be issued to the Seabrook Station.
B. Skud - 2 Thank you for your interest in this matter. We intend to keep the public fully informed of our review and inspection results, as this matter continues forward in the license renewal review process. The NRC is committed to ensuring the continued safe operation of U.S. Nuclear Power Plants, including the Seabrook Station.
ennis ,
Projects Branch Division of Licens Office of Nuclear Docket No. 50-443 cc: Listserv
ML12279A291 (Pkg.); ML12244A548 (Incoming);
ML12279A288(Response) *via email OFFICE I PM:RPB1 :DLR LA:RPB1 :DLR* OGC (NLO) BC:RPB1 :DLR NAME PMilano YEdmonds MSmith DMorev DATE 10/10/12 10/10/12 10/12/12 10/17/12