ML22131A135

1 to Updated Final Safety Analysis Report, Cover Letter and Information on Enclosures 1 to 7

ML22131A135
Person / Time
Site:	Seabrook
Issue date:	05/05/2022
From:	Booth B NextEra Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML22131A110	List: ML22131A088 ML22131A089 ML22131A090 ML22131A091 ML22131A092 ML22131A093 ML22131A094 ML22131A095 ML22131A096 ML22131A097 ML22131A098 ML22131A099 ML22131A100 ML22131A101 ML22131A102 ML22131A103 ML22131A105 ML22131A106 ML22131A107 ML22131A108 ML22131A109 ML22131A111 ML22131A116 ML22131A117 ML22131A120 ML22131A121 ML22131A122 ML22131A123 ML22131A124 ML22131A125 ML22131A126 ML22131A127 ML22131A129 ML22131A130 ML22131A131 ML22131A135
References
SBK-L-22042
Download: ML22131A135 (18)

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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