ML19101A144
| ML19101A144 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/22/2019 |
| From: | Mccartney E NextEra Energy Seabrook |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19101A148 | List:
|
| References | |
| SBK-L-19033 | |
| Download: ML19101A144 (21) | |
Text
March 22, 2019 10 CFR 50.59(d)(2) 10 CFR 50.71(e)
Docket 50-443 SBK-L-19033 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Seabrook Station NEXTera ENERGY~
SEABROOK 10 CFR 50.59 Report, Revision 19 to the Seabrook Station Updated Final Safety Analysis Report, Revision 16 to "Fire Protection Safe Shutdown Capability (1 OCFR50, Appendix R)," Revision 17 to "Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A" and Revision 157 to the Technical Requirements Manual NextEra Energy Seabrook, LLC (NextEra) encloses the 10 CFR50.59 Report, Revision 19 to the Seabrook Station Updated Final Safety Analysis Report (UFSAR), Revision 16 to "Fire Protection Safe Shutdown Capability (1 OCFR50, Appendix R)," Revision 17 to "Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A" and Revision 157 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 August 1, 2017 through December 31, 2018. UFSAR Revision 19 incorporates approved and implemented design changes and UFSAR changes identified through December 31, 2018. 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 UFSAR is provided in its entirety on CD-ROM in Portable Document Format (PDF).
Changes from Revision 18 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.
Ab D ¥'
NextEra Energy Seabrook, LLC PO Box 300, Seabrook, NH 03874
U.S. Nuclear Regulatory Commission SBK-L-19033/Page 2 The summaries of 10 CFR 50.59 evaluations for design changes incorporated in Revision 19 of the UFSAR are attached as Enclosure 1. No 10 CFR 50.59 evaluations were performed for other activities during the reporting period. Enclosure 2 provides a summary for changes to the UFSAR incorporated using the guidance ofNEI 98-03, "Guidelines for Updating Final Safety Analysis Reports." is a listing of UFSAR Change Requests (UFCRs) incorporated in UFSAR Revision 19 during the reporting period. The affected Sections, Tables and Figures are provided for each UFCR. 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 Report and Enclosure 6 contains UFCRs incorporated in the Technical Requirements Manual.
One copy of the UFSAR revision 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. Kenneth J. Browne, Licensing Manager, at (603) 773-7932.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on MA,YLL--1 LL Sincerely,
- --rYl~ /
Eric McCartney O
Regional Vice President NextEra Energy Seabrook, LLC
, 2019 cc:
NRC Region I Administrator NRC Project Manager, Project Directorate 1-2 NRC Senior Resident Inspector Enclosed CD Listing:
CD 1, 39 files, 646,297,859 bytes CD 2, 3 files, 46,712,725 bytes
Seabrook Station 10 CFR 50.59 Report, Enclosure 1 to SBK-L-19033 Summary Report of Facility Changes, Tests, and Experiments Completed in Accordance with the Requirements of 1 OCFR50.59 for Revision 19 of the Updated Final Safety Analysis Report
Seabrook Station IO CFR 50.59 Report, Enclosure I 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 15-002 Summary Description and
Purpose:
EC 145303, SSPS Circuit Board Replacement This design change package (EC 145303) approves the replacement of Seabrook Unit 1 Westinghouse Solid State Protection System (SSPS) original design printed circuit boards with the Westinghouse new design boards. The SSPS boards are being replaced due to obsolescence issues of the original design boards and to improve reliability. The approved boards are for use in the control board demutliplexing cabinets 1-MM-CP-25 & 30 and Main SSPS cabinets l -MM-CP-12 & 13. The replacement boards are all designed to be fit and function replacements for the original design SSPS boards.
Evaluation Summary:
This design change and 1 OCFR50.59 Evaluation are based on work performed by Westinghouse and the Pressurized Water Reactor Owners Group (PWROG) in support of upgrading SSPS to the new design boards. The PWROG submitted Topical Report (TR), WCAP-17867-P, Revision 1, "Westinghouse SSPS Board Replacement Licensing Summary Report" (approved version is Reference 13) to the Nuclear Regulatory Commission (NRC) for review and approval.
The TR documents the design process, design details, analyses, manufacturing controls, and verification process that was used for the new design SSPS boards. The results provide a comprehensive summary that concludes that the installation of the new design SSPS boards maintain or improve upon the original design board reliability and functional requirements for the SSPS. Additionally, no unanalyzed failures are introduced and the consideration of the software common cause failures (CCF) that would compromise SSPS equipment operations is eliminated.
The NRC issued the Final Safety Evaluation Report (FSE) for WCAP-17867-P, Rev. 1 (included in reference 13) on September 19, 2014. The NRC FSE states in general, the new design boards can be used to replace the original design boards.
Based on the 1 OCFR50.59 Evaluation performed and the NRC FSE it is concluded that a 10CFR50.59, License Amendment is not required.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 1 10 CFR 50.59 Evaluation 18-001 Summary Description and
Purpose:
EC 289694, Containment Model Update for NSAL-11-5 and NSAL 14-2 This activity updates the Seabrook GOTHIC containment response analysis performed as part of the stretch power uprate and its base-deck calculation. Specifically, this change incorporates three updates:
Updates the assumed droplet size to 660 microns based on a review of vendor test data.
Updated the uprate GOTHIC model in accordance with NRC approved Topic Report DOM-NAF-3 NP-A (ML063190467) with some conservative exceptions.
Incorporates the latest mass and energy release input due to issues identifies in Nuclear Safety Advisory Letter NSAL-14-2.
Evaluation Summary:
A 10 CFR 50.59 screening was performed and the following two (2) items screened in and required performance of a 50.59 evaluation:
- 1. NSAL-11-5 and NSAL-14-2 identified modeling issues that impacted the long term LOCA Mass and Energy (M&E) releases that were used as in input to the GOTHIC SPU analysis.
- 2. The updated Seabrook verification model uses GOTHIC 8.0 in lieu of GOTHIC 7.0, 7.1 or 7.2 which are discussed in DOM-NAF-3 NP-A.
Reanalysis of the confirmatory GOTHIC model, developed as part of the power uprate project and used to determine the containment peak pressure and temperature during a LOCA, to include new mass and energy values resulting from Westinghouse NSAL-11-5 and NSAL-14-2 (Update
- 1) and modelling updates (Update 3). The new mass and energy values had a minimal impact on the confirmatory analysis results and remained bounded by the original CONTRAST analysis.
Specifically, the projected piping temperatures increased during a design basis accident but remained well below their qualification analysis for a faulted condition. All other parameters remain bounded by the original DBA analysis. Therefore, the new mass and energy releases results in a minimal increase likelihood of occurrence of a malfunction of an SSC important to safety previously evaluat~d in the UFSAR.
This 50.59 Evaluation was perfonned for the activity due to the potential effect on methods of evaluation used in containment analysis. Methods of evaluation described in the UFSAR are subject to criterion 10 CFR 50.59(c)(2)(viii) if they are used in analysis that demonstrate that the design basis limits of fission product barriers are met. Methods of evaluation are described as the calculational framework used for evaluating behavior or response of the facility or an SSC.
As described in NEI 96-07 Revision 1, section 4.3.8, the use of a different method of evaluation (i.e. Topical Report DOM-NAF-3) can be used if that methodology has been previously approved by the NRC. It was demonstrated that GOTHIC versions 7.2 and 8.0 produce results that are essentially the same for Seabrook's containment model.
As a result, the changes of this activity do not require prior NRC approval.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 1 10 CFR 50.59 Evaluation 18-002 Summary Description and
Purpose:
EC 290987, Disable Main Turbine Automatic High Vibration Trip Function EC 290987 is a temporary configuration change that will change the main turbine high vibration input to the turbine trip from an automatic to a manual trip.
Evaluation Summary:
This activity involved a SSC (Turbine Supervisory Instrumentation) whose failure could initiate a transient by causing a turbine trip which would result in a reactor trip. Additionally, this activity fundamentally alters the existing means of performing or controlling a design function.
The automatic high vibration input to the design function (turbine trip) is being replaced by a manual action.
This activity temporarily disconnects the Turbine Vibration High Trip Signal from the Emergency Trip System (ETS) of the Main Turbine, disabling the Turbine Vibration High Trip signal from the automatic Turbine Trip design function. This logic change does not introduce any physical changes of hardware or software and the individual instruments and signals available for a Turbine Trip remain functional. Therefore, this activity does not result in a more than minimal increase in accidents or malfunctions previously evaluation in the UFSAR. This change also does not create a new type of event not previously evaluated in the UFSAR. This 50.59 evaluation concluded that this activity does not require prior NRC approval.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 1 10 CFR 50.59 Evaluation 18-003 Summary Description and
Purpose:
EC 290992, RCP UV RX Trip Response Time Margin Reallocation EC 290992 increases the protection system overall response delay for the Reactor Coolant Pump (RCP) Undervoltage (UV) Reactor (RX) Trip function from the existing < 1.5 seconds to < 2.25 seconds.
A 50.59 screening was performed and the following item screened in and required performance of a 50.59 evaluation:
- 1. The proposed change to the overall RCP UV trip response time delay required re-analysis of the UFSAR-described safety analysis.
Evaluation Summary:
The EC change in the RCP UV trip response time will not impact how electrical power is supplied to the RCPs, nor will it impact the likelihood or frequency of occurrence of an event which could cause a simultaneous loss of electrical power to all four RCPs. With the change to the RCP UV trip response time, the reactor is still tripped in the(Partial Loss of Flow) PLOF event by the low flow trip with a 1.0 second delay (which has not been changed). The DNBR will change due to an increase in the RCP UV trip delay time to 2.25 seconds, however, the revised DNBR is still above the safety analysis limit. The RCP UV trip response time change does not alter the consequences of a (Complete Loss of Flow) CLOF accident, nor does it introduce a new type of potential malfunction. This change also does not create a new type of event not previously evaluated in the UFSAR. This 50.59 evaluation concluded that this activity does not require prior NRC approval.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 1 10 CFR 50.59 Evaluation 18-004 Summary Description and
Purpose:
EC 291808, Issue Calculation for EWF Pump Exhaust Stack Tornado Missile This activity calculates the impact probability of a tornado missile on the Turbine Driven Emergency Feedwater (TDEFW) pump exhaust stack on top of the EFW pumphouse. Further, this change incorporates the stack as a new missile target in Seabrook's design basis.
Specifically, it is considered a safety related component not located in a tornado protected structure. The TDEFW pump exhaust stack calculation and analysis methodology are similar to other small targets at Seabrook. The activity in the scope of this 50.59 evaluation is the adverse impact of increasing the tornado missile risk due to the addition of a new target.
Evaluation Summary:
This activity calculates the impact probability of a tornado missile on the TDEFW pump exhaust stack on top of the EFW pumphouse and incorporates the stack as a new missile target. Per NEI 96-07, design changes associated with natural phenomena are considered to potentially cause malfunctions. Using the same level of detail as existing small targets to assess the TDEFW pump exhaust stack, there is no more than a minimally increase in the likelihood of a malfunction. This activity does not create any new malfunctions as tornado missiles are already considered in Seabrook's UFSAR. The radiological consequences of this activity are no more than minimal. This activity does not impact any design basis limits for fission product barriers and follows methodology consistent with Seabrook's licensing basis. This 50.59 evaluation concluded that this activity does not require prior NRC approval.
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Seabrook Station IO CFR 50.59 Report, Enclosure 1 10 CFR 50.59 Evaluation 18-005 Summary Description and
Purpose:
EC 145020 - 7300 System Printed Circuit Board Upgrades EC145020 R/013 approves the installation and use ofre-designed Westinghouse 7300 Process Control System printed circuit boards (PCBs). As evaluated in the screening, all but the re-designed 12NLL PCBs are equivalent performance, operating characteristics and design function and screen out of the 10 CFR 50.59 Evaluation process. This 10 CFR 50.59 Evaluation is specifically written to address the design activity for installation and use of the new digital Westinghouse 7300 12NLL PCB.
Evaluation Summary:
The 12NLL PCBs are more reliable than the original design NLL PCBs, and therefore, there would be a reduction in the frequency of occurrence of an accident associated with the 7300 PPS. The 12NLL PCBs do not result in more than minimal increase in the likelihood of occurrence of malfunctions. The 12NLL PCBs are more reliable than the original design NLL PCBs as documented in the MTBF calculations; therefore, the 12NLL PCBs will not result in more than a minimal increase in the likelihood of occurrence of a malfunction. Therefore, the installation of the 12NLL PCBs does not impact any of the design bases, including the environmental qualification impacts. Therefore, the proposed activity does not adversely affect other equipment used for accident mitigation such that the consequences of an accident are more than minimally increased. The 7300 PPS design functions are the same and are not changed or modified by the installation of the 12NLL PCBs, therefore all consequences are bounded by the events evaluated in the UFSAR. As described in previous evaluation questions, the 7300 PPS is not altered by the installation of the 12NLL PCBs. This activity does not impact the function of any plant SSC, nor does it create any new accidents of a different type, which would alter the current failure modes as discussed in UFSAR Chapter 7, Chapter 6 and 15 safety analyses.The installation of the 12NLL PCBs does not deviate from the analytical methods previously used to establish the design basis for the 7300 PPS and does not affect the method of evaluation used in the safety analysis. This 50.59 evaluation concluded that this activity does not require prior NRC approval.
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Seabrook Station IO CFR 50.59 Report, Enclosure 2 to SBK-L-19033 Summary 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 CFR 50.59 Report, Enclosure 3 The following provides a summary of changes incorporated in Revision 19 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 289861 Affected Sections, Tables, Figures UFSAR Section 3.9(B)
Description of Change: This activity adds a note in Section 3.9(B) discussion of snubbers to indicate that later editions of the ASME Code may be used as allowed by ASME Section XI, Para. IW A-4223. This is additional information for clarification.
EC 290022 UFSAR Table 2.3-14 Description of Change: The activity is an administrative correction to the title of Table 2.3-14.
EC 290031 UFSAR Section 1.8 Description of Change: The activity updates a document reference related to Oversight/QA training requirements to refer to the correct governing document.
EC 290074 UFSAR Section 3.2.1 Description of Change: The activity is an administrative change to remove excessive detail which is not relevant to the plants licensing basis.
EC 290875 UFSAR Section 2.5.4.Se.6 Description of Change: Editorial correction to change subsection 2.5.4.Se.6 to 2.5.4.Sc.6.
EC 291268 UFSAR Sections 9.2.2.1, 9.2.2.3.b and 9.5.1.2.c.8 Description of Change: Thi~ activity updates UFSAR sections to clarify the plant's licensing basis for PCCW system. The change clearly states that the heat tank capacity is used to provide system with the needed capacity during a design basis event. The design basis does not credit additional make-up from other sources, although additional sources of water are available during an emergency. This change provides clarifications to improve reading understanding.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 3 EC 291813 UFSAR Section 9.5.1.5 Description of Change: This activity updates job titles and responsibilities in UFSAR Section 9.5.1.5, Personnel Qualification and Training (Fire Protection). Revising the job titles and requirements does not change the meaning or substance of the information provided. This change is editorial.
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Seabrook Station 10 CFR 50.59 Report, Enclosure 3 to SBK-L-19033 Listing ofUFSAR Change Requests (UFCRs/UCRs) Incorporated in Updated Final Safety Analysis Report, Revision 19
Seabrook Station 10 CFR 50.59 Report, Enclosure 3 UFCR/UCR Number Affected Sections EC283632 8.2 EC287676 10.4 EC287678 3.9(N), 4.3, 7.7 EC287679 8.3.1.1.d EC287966 8.3.2.1.b EC289591 5.4, 7.1, 7.3, 10.3 EC289694 6.2 EC289778 5.4 EC289861 3.9(B)
EC289886 9.4 EC290022 EC290031 1.8 EC290074 3.2 EC290705 12.5 Affected Tables 1.3-1, 1.3-2 8.3-1, 8.3-2, 8.3-5 2.3-14 12.5-1 1 of 2 Affected Figures 7.7-9
Seabrook Station 10 CFR 50.59 Report, Enclosure 3 UFCR/UCR Number Affected Sections EC290875 2.5 EC290919 8.2.1.3.e EC290992 EC291170 2.2 EC291268 9.2.2.1, 9.2.2.3.b, 9.5.1.c.8 EC291427 EC291808 6.8 EC291813 9.5.1.5 EC292531 1.8, 15.7, App 15C Affected Tables Affected Figures 8.2-1 7.2-3, 15.0-4, 15.3-1 15.3-3 thru 15.3-5 2.2-1 8.3-1, 8.3-2 15.7-19, 15.7-20, 15.7-21, 15C-5 2 of 2 2.2-1, 2.2-5
Seabrook Station 1 OCFR50.59 Report, Enclosure 4 to SBK-L-19033 Listing of UFSAR Change Requests (UFCRs) Incorporated in Fire Protection Safe Shutdown Capability (1 OCFR50, Appendix R), Revision 16
Seabrook Station 1 OCFRS0.59 Report, Enclosure 4 UFCR/UCR Affected Sections Affected Tables/
Affected Figures Number Tabulations EC287679 MCR 3.1.3.17 EC290025 3.2 MCR 3.1.3.12, RSS 3.1.3.12 EC290816 3.2, 3.7 EC290867 3.2 EC291451 3.3.3.1, 3.3.5 EC291941 MCR 3.1.3.12, RSS 3.1.3.12 1 of 1
Seabrook Station 1 OCFRS0.59 Report, Enclosure 5 to SBK-L-19033 Listing of UFSAR Change Requests (UFCRs) Incorporated in Evaluation and Comparison to BTP APCSB 9.5-1, Appendix A Revision 17
Seabrook Station 1 OCFRS0.59 Report, Enclosure 5 UFCR/UCR Number EC283133 EC289722 Affected Sections F.2,Tab 5 F.2, Tab 5, 8 Affected Tables 1 of 1 Affected Figures
Seabrook Station 1 OCFRS0.59 Report, Enclosure 6 to SBK-L-19033 Listing of UFSAR Change Requests (UFCRs) Incorporated in Revisions 154 through 157 of the Technical Requirements Manual
Seabrook Station 1 OCFR50.59 Report, Enclosure 6 UFCR/UCR Affected Sections Affected Tables Affected Figures Number EC284920 TR-13, TR-14 EC287676 TR-33 EC287678 TR-13 EC290437 TR-13, TR-14 EC290642 COLR EC290680 TR-24 EC290992 2.2.1 1 of 1