ML20323A141
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United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Seabrook Station NEXTera EN E~R,,,,;,,,;;;;--~-....
October 22, 2020 10 CFR 50.59(d)(2) 10 CFR 50.71(e) 10 CFR 54.37(b)
Docket 50-443 SBK-L-20124 SEABROOK 10 CFR 50.59 Report, Revision 20 to the Seabrook Station Updated Final Safety Analysis Report, Revision 17 to "Fire Protection Safe Shutdown Capability (1 0CFR50, Appendix R)," Revision 18 to "Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A", Revision 162 to the Technical Requirements Manual, 10 CFR 54.37(b) Aging Management Review Summary, and Summary of Commitment Changes NextEraEnergy Seabrook, LLC (NextEra) encloses the 10 CFR50.59 Report, Revision20 to the Seabrook Station Updated Final Safety Analysis Report (UFSAR), Revision 17 to "Fire Protection Safe Shutdown Capability (10CFR50, Appendix R)," Revision 18 to Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A" and Revision 162 to the Technical Requirements Manual. The 10 CFR 50.59 Report and the UFSAR are submitted pursuant to the requirements ofl0 CFR 50.59(d)(2) and 10 CFR 50.71(e). The 10 CFR 50.59 report covers the period from January 01, 2019 through June 30, 2020. UFSAR Revision 20 incorporates approved and implemented design changes and UFSAR changes identified from January 01, 2019 through June 30, 2020. 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 January 01, 2019 through June 30, 2020.
The UFSAR is provided in its entirety on CD-ROM in Portable Document Format (PDF). Changes from Revision 19 are indicated by a change in revision number and a vertical line (revision bar) in the margin next to the change. 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.
NextEra Energy Seabrook, LLC PO Box 300, Seabrook, NH 03874
U.S. Nuclear Regulatory Commission SBK-L--20124/Page 2 The summaries o~ 10 CFR 50.59 evaluations for design changes incorporated in Revision 20 of the UFSAR are attached as Enclosure 1. Enclosure 2 provides a summary for changes to the UFSAR incorporated using the guidance of NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports." Enclosure 3 is a listing ofUFSAR Change R~uests (UFCRs) incorporated in UFSAR Revision 20 during the reporting period. The affected Sections,_Tables and Figures are provided for each UFCR. Enclosure 4 contains UFCRs incorporated in the Fire Protection Safe Shutdown Capability Report. Enclosure 5 provides the UFCRs incorporated in Evaluation and Comparison to BTP APCSB 9.5-1 ~eport. Enclosure 6 contains UFCRs incorporated in the Technical Requirements Manual. Enclosure 7 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 8 provides a summary ofRe~atory Commitment Changes.
One copy of the UFSAR revision on CD-ROM is being submitted to the Document Control Desk, Washington, DC, aj_ong* with a copy to the Region I Regional Office and a copy to the Resident Inspector at Seabrook Station.
Shoul_d you have any questions regarding this matter, please contact Mr. Kenneth J. Browne, Safety Assurance and Learning Site.Director, at (603) 773-7932.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on o~ +okr:::: Z "l.
-, 2020 Sincerely, Eric McCartney 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, 636,983,296 bytes CD 2, 3 files, 103,178,240 bytes
Seabrook Station 10 CFR 50.59 Report, Enclosure 1 to SBK-L-20124 Summary ReportofFacility Changes, Tests, and Experiments Completed in Accordance with the Requirements of 1 0CFR50.59 for Revision 20 of the Updated Final Safety Analysis Repor;t
Seabrook Station 10 CPR 50.59 Report, Enclosure 1 Design Change Evaluations Design changes documented iri the following Engineering Changes (EC) were installed during the period covered by the 10 CPR 50.59 Report. A<l0 CPR 50.59 evaluation was performed for the ECs identifie:d below. For each of the evaluations performed, there were no activities requiring prior NRC approval identified.
10 CFR 50.59 Evaluation 18-006 Summary Description and.Purpose:
EC 291611, MSLB Containment Response Verification Revision This EC updates the Seabrook GOTHIC containment analysis verification performed during the Stretch Power Uprate (SPU). It determines containment parameters used to evaluate fission product barriers such as maximum containment temperature and pressure during a MSLB. The update incorporates larger containment spray droplet size which results in slightly higher pressure and temperature response. This is an evaluation of an existing analysis, and does not
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modify the plant in any way. This activity updates the MSLB Containment response calculated to reflect the most recent basedeck model. This activity does not change any UFSAR methodology. This activity updates the MSLB Containment Response analysis to reflect the model consistent with UFSAR Containment verification analysis description.
Evaluation Summary:
Reanalysis of the confirmatory containment response GOTHIC model, developed as part of the power uprate project and used to determine the containment peak pressure and temperature during a MSLB, includes a larger droplet size. It also updates the MSLB model to reflect the revised basedeck approved in EC 289694.
This 50.59 Evaluation was performed for the activity due to the larger droplet size increasing the containment pressure, and temperature response. This change does not result in more than a minimal increase in the radiological consequences of an accident There is no change to a UFSAR described methodology associated with this change. As a result, the changes of this activity do not require a License Amendment Request.
10 CFR 50.59 Evaluation 19-001 Summary Description and
Purpose:
EC 292693, Revise TR 23 to Extend Control Valve Testing Intenral EC 292693 revises Technical Requirement 23 to change the frequency for testing the High Pressure Turbine Control Valves from once per 90 days to once per 150 days, and revises UPS.AR Sectiop. 3.5 to describe the method of obtaining an input parameter to the Turbine Missile Analysis.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 1 Evaluation Summary:
The proposed change affects the reliability of the n,rrbine control valves and therefore the reliability of the Turbine Overspeed Protection System. The control valves and the Turbine Overspeed Protection System do not function as the initiator of any accident previously evaluated in the UFSAR. Therefore, the change to the turbine control valve testing frequency does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR The change in testing frequency for the-turbine control valves results in a probability oflow trajectory missile damage that is well below the acceptance criteria of lxl 0-6 per year and a probability of high trajectory missile damage on any s-afety related structure that is below tl;ie acceptance criteria of lxl0-7 per year. The increase in the probability of a failure of a turbine control valve is increased by approximately 86%, which is less than the factor of two cited in NEI 96-07, Revision 1, "Guidelines for 10 CFR 50.59 Implementation" as constituting the threshold for a "More the Minimal" increase. Therefore, the proposed change does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR The turbine control valves and the Turbine Overspeed Protection System do not function to mitigate the consequences of any accident evaluated in the UFSAR The decrease in reliability does not affect the ability of any other system or component to mitigate the consequences of any accident Therefore the proposed activity does not result in more than a minimal increase in the radiological consequences of an accident previously evaluated in the UFSAR.
This 50.59 evij).uation concluded that this activity does not require prior NRC approval.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 2 to SBK-L-20124
$ummary of Changes to the Updated Final Safety Analysis Report Incorporated Using the,Guidance ofNEI 98-03, "Guidelines for Updating Final Safety Analysis Reports"
Seabrook Station 10 CPR 50.59 Report, Enclosure 2 The following provides a summary of changes incorporat~d in Revision 20 of the Updated Final
- Safety Analysis Report using the guidance contained in NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports."
UFCR/UCR Number EC 290087 Affected Sections, Tables, Figures UFSAR Section 9.4.15.2.h, Table 9.4-19 Description of Change: Sections 9.4.15.2.h and Table 9.4-19 describe the air conditioning in the Secondary Alarm Station (SAS) UninterruptibkPower Supply (UPS) Room. These sections were updated to describe the replacement air conditioning. Specifically, the condenser unit is moved from within the Turbine Building to the Heater Bay Roof; and the capacity is reduced from 3 tons (36,000 Btu/hr) to 2-1/2 tons (30,000 Btu/hr).
EC 292807 UFSAR Section 13.1.1.1 Description of Change: This activity revises Section 13.1.1.1 to match the language in the Quality Assurance Topical Report (QATR) for the Director of Engineering.
EC 292920 UFSAR Table 1.1-1 Description of Change: The activity deletes Table 1.1-1 from the UFSAR. UFSAR Table 1.1-1 is a cross reference list of UFSAR figure numbers and design drawings numbers, including revision and issue dates.
EC 293144 UFSAR Section 8.2.1.4.g, 9.5.2.2.b.2, 9.5.2.3.b Description of Change: The activity revises the UFSAR relay room configuration description to be consistent with the equipment modifications made by this design change. It also removes
- the 48 VDC system components from the relay room equipment list in the UFSAR.
EC294470 UFSAR Section 9.3, 13.1, 13.1.3.2 Description of Change: Editorial correction to Chapter 9.3, Page 12, refers to the Steam Generator Blowdown sample sink flow being routed-via a TMOD (Temporary Modification).
TMOD has been removed. Chapter 13.1 has been revised to reflect organiz.ational structure changes. Section 13.1.3.2, Qualifications of Station Personnel, was also deleted. This paragraph refers to the station management during start-up. This information is historical.
Seabrook Station 10 CFR 50.59 Report, Enclosure 3 to SBK-L-20124 Listing ofUFSAR Change Requests (UFCRs/UCR.s) Incorporated in Updated Final Safety Analysis Report, Revision 20
Seabrook Station 10 CPR 50.59 Report, Enclosure 3 UFCR/UCR Number EC13552 EC284000 EC287319 EC287967 EC289197 EC290087 EC291611 EC292628 EC292653 EC292807 EC292920 EC293144 EC293173 Affected Sections 9.3.5.2a, 9.3.5.2c, 9.3.2.2a.3-6.8, 8.4, 9.2 8.2 8.3.2.1.b 9.4.15.2.h 6.2.1.8 3.8.1.3, 3.8.1.4, 3.8.3.3, 3.8.3.5, 3.8.3.6, 3.8.3.7, 3.8.4.3, 3.8.4.4, 3.8.4.5, 3.8.4.6, 3.8.4.7, 3.8.6, 3.9(B) 3.5 13.1.1.1 8.2.1.4.g, 9.5.2.2.b.2, 9.5.2.3.b 8.3d.l.g 1 of 2 Affected Tables 3.9(B)-27, 3.9(B)-28 9.4-19 3.8-1, 3.8-14, 3.8-16, 3.8-17, 3.8-18 1.1-1 Affected Figures -
9.3-18, 9.3-19, 9.3-20, 9.3-23, 9.3-24, 11.2-2, 1.1-1 8.2-5, 8.2-10
Seabrook Station 10 CFR 50.59 Report, Enclosure 3
-UFCR/UCR Number EC293343 EC293641 EC293900 EC293964 EC294424 EC294470 EC294927 Affected Sections 8.3.1.1.g Chapter 18, 18.1.1, 18.1.2, 18.1.3, 18.1.4, 18.1.5, 18.1.6, 18.2.1, 18.2.2,
- 18.2.3, 18.2.4, Appe.ndix 18A 7.2.1.1.c.2, 10.2.2.4 9.3, 13.1, 13.1.3.2 3.9(N), 4.2, 4.3, 7.7 2 of 2 Affected Tables Affected Figures 8.3-1, 8.3-2 8.3-1
Seabrook Station 1 0CFRS0.59 Report, Enclosure 4 to SBK-L-20124 Listing ofUFSAR Change Requests (UFCRs) Incorporated in Fi_re Protection Safe Shutdown Capability (1 OCFR50, Appendix R), Revision 17
Seabrook Station 10CFRS0.59 Report, Enclosure 4 UFCRJUCR Number EC294568 Affected Sections 3.4-2, 3.4-4 Affected Tables/
Tabulations 1 of 1 Affected Figures
Seabrook Station 10CFRS0.59 Report, Enclosure 5 to SBK-L-20124 Listing of UFSAR Change Requests (UFCR.s) Incorporated in Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A Revision 18
Seabrook Station 10CFRS0.59 Report, Enclosure 5 UFCR/UCR Number EC290084 EC293456
- Affected Sections
- F.2,Tab 15 F.2, Tab 9 Affected Tables
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Seabrook Station 1 0CFRS0.59 Report, Enclosure 6 to SBK-L-20124 Listing ofUFSAR Change Requests (UFCRs) Incorporated in Revisions 158 through 162 of the Technical Requirements Manual
Seabrook Station 10CFRS0.59 Report, Enclosure 6 UFCR/UCR Affected Sections Affected Tables Affected Figgres Number EC292653 TR-23 EC292754 1
EC293102 TR-5.5 EC294544 TR-17 EC293360 6
EC294153 TR-35, TR-36 EC293173 TR-13, TR-14 1 of 1
\\ to SBK-L-20124 10 CFR 54.37(b)
Aging Management Review Summary
Seabrook Station 10CFR50.59 Report, Enclosure 7 10 CFR 54.37(b) states tha("After the renewed license~ 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 manag-ement review or evaluation of time-limited aging analysis in accordance with §54.21: 1bis FSAR update must describe ho\\V 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."
1bis summary comprises of a period.fr1Jm 1/1/2019 through 6/30/2020 to align with the UFSAR update as required within110 CFR 50.71(e). In addition, this summary includes a review of engineering changes completed in-the time period of3/l/2018-12/31/2018 because of the time frame of the Eighth Annual Update (Accession Number-ML18172A045), and receipt of the Renewed Facility Operating License issued on 3/12/2019.
During this reporting period, there was one new component identified to be added to the Aging Management Program for Seabrook Station identified within EC UCR: 289197. Below describes the component ID and 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.
1-FW-V-54 will be added to the Water Chemistry Aging Management Program LRAP-M002, One Time Inspection Aging Management Program LRAP-M032, and External Surfaces Aging Management Program LRAP-M036.
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Seabrook Station 10CFR50.59 Report, Enclosure 8 to SBK-L-20124 Summary of Commitment Changes during the Period of January-I, 2019 through June 30, 2020.
Seabrook Station 10CFRS0.59 Report, Enclosure 8 Below is a summary for one Commitment change made during the period of January 1, 2019 through June 30, 2020. The Commitment change was performed in accordance with station procedures and guidance provided within Nuclear Energy Institute (NEI) 99 Guidelines for Manager NRC Commitment Changes. The following Commitment change fo:i; Seabrook Station requires notification to the NRC.
Commitment Original Revised Change Request Basis for Revision Number Commitment Commitment NRC Bulletin NRC Bulletin 85-01 and Generic Letter 85--01.
EFW pump 88--03 states to Emergency Feed water discharge monitor once per 18--01 (EFW) Pump temperature shift. Technical discharge checks revised Specifications Table to every 12 1.1, Frequency temperature hours.
Notation, "S" is checks every defined as "at least four hours.
once per-12 hours."
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