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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:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22131A1082022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2.3, Figures ML22131A1262022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Appendix a - C ML22245A0022022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2.4, Figures Redacted ML22131A1012022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix a, Onsite Meteorological Data Summaries, November 1971-March 1973 ML22131A1112022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix J - K ML22131A1232022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix B, Onsite Meteorological Data Summaries, April 1979-March 1980 ML22131A1222022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications and Chapter 17, Quality Assurance ML22131A1022022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix G - I ML22131A1092022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix C, Geologic Investigations of the Scotland Road Fault (Clinton- Newbury Fault), Newbury, Massachusetts, and Portsmouth Fault Investigations ML22131A1062022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22245A1002022-05-0505 May 2022 9 to Evaluation and Comparison to BTP Apcsb 9.5-1, Appendix a - Redacted ML22131A1072022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22131A0952022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22131A0922022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML22131A1212022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix D, Geologic Bedrock Logs of Boring in the Site Area ML22131A1032022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix E, Historical Earthquakes in the Site Vicinity ML22131A1352022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Cover Letter and Information on Enclosures 1 to 7 ML22131A1202022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22245A0532022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Section 2.1, Figures - Redacted ML22131A0942022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs ML22131A1242022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Appendix D - F ML22131A0912022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22131A1302022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Appendix G, Part 2 and Appendix H ML22131A0882022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix L - R ML22131A0932022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 1, List of Effective Pages and Introduction and General Description of Plant ML22245A0422022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics - Redacted ML22131A1312022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Figures, Part 3 ML22131A0982022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2, Appendix F, Geotechnical Report - Reactor Borings, July 1974 ML22131A0992022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22131A1162022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22131A0892022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Appendix I, Report of Analysis of High Energy Line Breaks Outside Containment ML22131A1292022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML22245A0592022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2.5, Figures, Part 2_Redacted ML22245A0612022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted ML22131A1172022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems ML22131A1002022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Appendix G, Container Liner Anchor Load Tests, Part 1 ML22131A0972022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Figures, Part 1 ML22131A0902022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Figures, Part 2 ML22131A0962022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System SBK-L-22042, 1 to Updated Final Safety Analysis Report, Chapter 2.5, Figures, Part 1 Redacted2022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 2.5, Figures, Part 1 Redacted ML22131A1252022-05-0505 May 2022 1 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML21089A0732021-03-30030 March 2021 Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Section 2.2, Figures Redacted ML20323A1592020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3A Through Appendix 3C ML20323A1522020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems ML20323A1552020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3I ML20323A1512020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2J Through Appendix 2K ML20323A1582020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3D Through Appendix 3F ML20323A1572020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3G, Part 1 ML21089A3662020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Section 2.5, Figures, Redacted ML21089A0822020-10-22022 October 2020 Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Section 2.4, Figures - Redacted 2022-05-05
[Table view] |
Text
NEXTera ENERGY ~
SEABROOK May 05, 2022 10 CFR 50.59(d)(2) 10 CFR 50.71(e) 10 CFR 54.37(b)
Docket 50-443 SBK-L-22042 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Seabrook Station 10 CFR 50.59 Report, Revision 21 to the Seabrook Station Updated Final Safety Analysis Report, Revision 18 to "Fire Protection Safe Shutdown Capability (1 0CFR50, Appendix R),"
Revision 19 to "Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A", Revision 165 to the Technical Requirements Manual, 10 CFR 54.37(b) Aging Management Review Summary, and Summary of Commitment Changes NextEra Energy Seabrook, LLC (NextEra) encloses the 10 CFR50.59 Report, Revision 21 to the Seabrook Station Updated Final Safety Analysis Report (UFSAR), Revision 18 to "Fire Protection Safe Shutdown Capability (1 0CFR50, Appendix R)," Revision 19 to "Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A" and Revision 165 to the Technical Requirements Manual.
The 10 CFR 50.59 Report and the UFSAR are submitted pursuant to the requirements of 10 CFR 50.59(d)(2) and 10 CFR 50.71(e). The 10 CFR 50.59 report covers the period from July 01 , 2020 through December 31, 2022. UFSAR Revision 21 incorporates approved and implemented design changes and UFSAR changes identified from July 01 , 2020 through December 31 , 2022. The incorporated changes to the UFSAR have been reviewed in accordance with 10 CFR 50.59. The reviews determined that these changes did not require prior NRC approval. The Aging Management Review Summary is pursuant to 10 CFR 54.37(b). The Summary of Commitment Changes covers the period of July 0 1, 2020 through December 31, 2022.
The UFSAR is provided in its entirety on CD-ROM in Portable Document Format (PDF). The List of Effective Pages contained within the UFSAR provides a listing of each page and its revision number with a revision bar indicating which pages contain changes. The controlled drawings referenced in the UFSAR are not being provided as they have the potential to contain security-related information. The drawings are available on site for NRC review. The Fire Protection Safe Shutdown Capability Report, Evaluation and Comparison to BTP APCSB 9.5-1 Report and the Technical Requirements Manual are also provided on CD-ROM. /4-b 5 3
)-!>Dip NextEra Energy Seabrook, LLC PO Box 300, Seabrook, NH 03874 (VI.~
U.S. Nuclear Regulatory Commission SBK-L-220042/Page 2 The summaries of 10 CFR 50.59 evaluations for design changes incorporated in Revision 21 of the UFSAR are attached as Enclosure 1. Enclosure 2 is a listing of UFSAR Change Requests (UFCRs) incorporated in UFSAR Revision 21 during the reporting period. The affected Sections, Tables and Figures are provided for each UFCR. Enclosure 3 contains UFCRs incorporated in the Fire Protection Safe Shutdown Capability Report. Enclosure 4 provides the UFCRs incorporated in Evaluation and Comparison to BTP APCSB 9.5-1 Report. Enclosure 5 contains UFCRs incorporated in the Technical Requirements Manual. Enclosure 6 contains a report describing how the effects of aging of newly-identified structures, systems or components (SSCs) will be managed, as required by 10 CFR 54.37(b). Enclosure 7 provides a summary of Regulatory Commitment Changes.
One copy of the UFSARrevision on CD-ROM is being submitted to the Document Control Desk, Washington, DC, along with a copy to the Region I Regional Office and a copy to the Resident Inspector at Seabrook Station.
Should you have any questions regarding this matter, please contact Mr. Matthew Levander, Regulatory Affairs Manager, at (603) 773-7631.
alty of pr*ry that the foregoing is true and correct.
6 '2022 Site Vice President - Seabrook Nuclear Power Plant NextEra Energy Seabrook, LLC cc: NRC Region I Administrator NRC Project Manager, Project Directorate I-2 NRC Senior Resident Inspector Enclosed CD Listing:
CD 1, 40 files CD 2, 3 files
Seabrook Station 10 CPR 50.59 Report, Enclosure 1 Enclosure 1 to SBK-L-22042 Summary Report of Facility Changes, Tests, and Experiments Completed in Accordance with the Requirements of 10CFR50.59 for Revision 21 of the Updated Final Safety Analysis Report
Seabrook Station 10 CPR 50.59 Report, Enclosure 1 Design Change Evaluations Design changes documented in the following Engineering Changes (EC) were installed during the period covered by the 10 CFR 50.59 Report. A 10 CFR 50.59 evaluation was performed for the ECs identified below. For each of the evaluations performed, there were no activities requiring prior NRC approval identified.
10 CFR 50.59 Evaluation 21-002 EC 295513, Exide Inverter ED-1-4 Replacement Summary Description and
Purpose:
This EC replaces non-vital UPS 1-ED-I-4 with a new 50 kVA Ametek UPS due to obsolescence issues. The new UPS employs digital firmware in place of analog control circuits that perform UPS control in four (4) functional areas; 1) charger/rectifier control, 2) inverter/static switch control, 3) alarm relay control and 4) local HMI control. The new UPS includes three position remote manual bypass switch to replace the existing 1-ED-I-2-B Exide UPS. The new UPS consists of a rectifier section, inverter section, and output static transfer switch. A manually operated 3-position Remote (external to the UPS enclosure) Manual Bypass Switch (RMBS) will allow complete isolation of the UPS to facilitate maintenance.
The UPS design function of initiating a plant transient upon loss of the UPS output is adversely impacted by a potential firmware common cause failure (CCF) that did not previously exist.
Evaluation Summary:
This 50.59 Evaluation was performed for the activity due to the UPS design function of initiating a plant transient upon loss of the UPS output is adversely impacted by a potential firmware common cause failure (CCF) that did not previously exist.
A qualitative assessment was completed, concluding that the failure likelihood introduced by the UPS digital controls upgrade is sufficiently low. With the failure likelihood introduced by the UPS digital controls upgrade being sufficiently low, the failure modes and effects analysis for the existing analog controlled UPS remains bounding for the new digitally controlled UPS and mitigation of accident consequences is not affected by the UPS replacement.
Therefore, the proposed UPS digital controls upgrade does not result in more than a minimal increase in the radiological consequences of an accident previously evaluated in the UFSAR.
10 CFR 50.59 Evaluation 21-003 EC 294176, Exide Inverter ED-1-2-B Replacement Summary Description and
Purpose:
Seabrook Station 10 CFR 50.59 Report, Enclosure 1 This EC replaces non-vital UPS 1-ED-I-2-B with a new 50 kV A Ametek UPS due to obsolescence issues. The new UPS employs digital firmware in place of analog control circuits that perform UPS control in four (4) functional areas; 1) charger/rectifier control, 2) inverter/static switch control, 3) alarm relay control and 4) local HMI control. The new UPS includes three position remote manual bypass switch to replace the existing 1-ED-I-2-B Exide UPS. The new UPS consists of a rectifier section, inverter section, and output static transfer switch. A manually operated 3-position Remote (external to the UPS enclosure) Manual Bypass Switch (RMBS) will allow complete isolation of the UPS to facilitate maintenance.
The UPS design function of initiating a plant transient upon loss of the UPS output is adversely impacted by a potential firmware common cause failure (CCF) that did not previously exist.
Evaluation Summary:
This 50.59 Evaluation was performed for the activity due to the UPS design function of initiating a plant transient upon loss of the UPS output is adversely impacted by a potential firmware common cause failure (CCF) that did not previously exist.
A qualitative assessment was completed, concluding that the failure likelihood introduced by the UPS digital controls upgrade is sufficiently low. With the failure likelihood introduced by the UPS digital controls upgrade being sufficiently low, the failure modes and effects analysis for the existing analog controlled UPS remains bounding for the new digitally controlled UPS and mitigation of accident consequences is not affected by the UPS replacement.
Therefore, the proposed UPS digital controls upgrade does not result in more than a minimal increase in the radiological consequences of an accident previously evaluated in the UFSAR.
Seabrook Station 10 CPR 50.59 Report, Enclosure 2 Enclosure 2 to SBK-L-22042 Listing ofUFSAR Change Requests (UFCRs/UCRs) Incorporated in Updated Final Safety Analysis Report, Revision 21
Seabrook Station 10 CPR 50.59 Report, Enclosure 2 UFCR/UCR Affected Sections Affected Tables Affected Figures Number EC290177 9.5-1 EC290426 8.2.1.3.a.1 EC291242 6.2.1.1.b.6 3.2-2 EC293028 1.8, 2.3.1.2.b.2, 2.3.6, 3.3-3, 3.5-11 3.3.2.1, 3.3.2.2.a, 3.3.2.2.b EC293297 2.3.3.3, Appendix 7A 2.3-37 EC294150 8.3.1.1.d 8.3-1, 8.3-2, 8.3-5 EC294176 8.3-1, 8.3-2 EC294291 8.3.l.l.c.7(a)(l)
EC295305 9.2-6 EC295375 6.1 (N).1.2, 6.5 .2.6, 6.3-1, 6.2-75, 6.3-9, 15.1.5.2.a.l 15.6-29 EC295513 8.3-1, 8.3-2 EC296081 5.3.1.6, 5.3.1.6.1, 5.3.4 EC296199 8.3.1.4.a EC296334 18.2.1.7, Appendix 18A EC296393 7.7.1.2 EC296604 7.2, 7.3 1 of 2
Seabrook Station 10 CFR 50.59 Report, Enclosure 2 UFCR/UCR Affected Sections Affected Tables Affected Figures Number EC296707 9.3 .4.2.f.2.d EC297068 4.3 1.6-1 2 of 2
Seabrook Station 10CFRS0.59 Report, Enclosure 3 Enclosure 3 to SBK-L-22042 Listing ofUFSAR Change Requests (UFCRs) Incorporated in Fire Protection Safe Shutdown Capability (1 0CFR50, Appendix R), Revision 18
Seabrook Station 10CFRS0.59 Report, Enclosure 3 UFCR/UCR Affected Sections Affected Tables/ Affected Figures Number Tabulations EC294150 MCR 3.1.3.17-39 EC294476 3.2 EC294978 MCR 3.1.3.1-11, RSS 3.1.3.1-4 EC295066 3.2 EC295513 3.2 MCR 3.1.3.17-43 EC296354 3.2, 3.3 EC297414 3.2 1 of 1
Seabrook Station 10CFRS0.59 Report, Enclosure 4 Enclosure 4 to SBK-L-22042 Listing ofUFSAR Change Requests (UFCRs) Incorporated in Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A Revision 19
Seabrook Station 10CFRS0.59 Report, Enclosure 4 UFCR/UCR Affected Sections Affected Tables Affected Figures Number EC290177 F.3, F.2 Tab 14 EC293031 F.2 Tab 5 EC294476 F.2 Tab 8 EC295066 F.2 Tab 8, F.2 Tab 11 EC295513 F.2 Tab 17 EC297414 F.2 Tab 8 1 of 1
Seabrook Station 10CFR50.59 Report, Enclosure 5 Enclosure 5 to SBK-L-22042 Listing of UFSAR Change Requests (UFCRs) Incorporated in Revisions 163 through 165 of the Technical Requirements Manual
Seabrook Station 10CFRS0.59 Report, Enclosure 5 UFCR/UCR Affected Sections Affected Tables Affected Figures Number EC290177 TR-7 EC294291 TR-13, TR-14 EC295375 6 EC296081 TR-4 EC296604 TR-19 EC297068 6 1 of 1
Seabrook Station 10CFRS0.59 Report, Enclosure 6 Enclosure 6 to SBK-L-22042 10 CFR 54.37(b)
Aging Management Review Summary 1 of 1
Seabrook Station 10CFR50.59 Report, Enclosure 6 10 CFR 54.37(b) states that "After the renewed license is issued, the FSAR update required by 10 CFR 50.7l(e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analysis in accordance with §54.21. This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in §54.4(b) will be effectively maintained during the period of extended operation."
This summary comprises of a period from 7/1/2020 through 12/31/2021 to align with the FSAR update as required within 10 CPR 50.71(e). In addition, this summary includes a review of engineering changes completed in the time period of 1/1/2019 to 12/31/2021.
During this reporting period, there were new components identified to be added to the Aging Management Program for Seabrook Station identified within EC291242. Below describes the applicable Aging Management Programs that will be used to ensure the effects of aging will be managed such that the intended function(s) will be effectively maintained during the period of extended operation.
New stainless steel filter housings and stainless steel piping will be added to the Water Chemistry Aging Management Program LRAP-M002. Stainless steel valves will be added to the Water Chemistry Aging Management Program LRAP-M002 and Closed-Cycle Cooling Water System Aging Management Program LRAP-M021. Non-ASME Carbon Steel Supports will be added to the Structures Monitoring Aging Management Program LRAP-S006.
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Seabrook Station 10CFRS0.59 Report, Enclosure 7 Enclosure 7 to SBK-L-22042 Summary of Commitment Changes during the Period of July 1, 2020 through December 31, 2021 1 of 1
Seabrook Station 10CFR50.59 Report, Enclosure 7 There were no changes made to Commitments during the period of July 1, 2020 through December 31, 2021.
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