IR 05000443/2022011
| ML22081A150 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/22/2022 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Coffey B Florida Power & Light Co |
| Gray M | |
| References | |
| IR 2022011 | |
| Download: ML22081A150 (10) | |
Text
March 22, 2022
SUBJECT:
SEABROOK STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS)
INSPECTION REPORT 05000443/2022011
Dear Mr. Coffey:
On February 10, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station and discussed the results of this inspection with Mr. Brian Booth, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Digitally signed by Melvin K.
Melvin K. Gray Gray Date: 2022.03.22 10:19:38-04'00'
Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket No. 05000443 License No. NPF-86
Enclosure:
As stated
Inspection Report
Docket Number: 05000443 License Number: NPF-86 Report Number: 05000443/2022011 Enterprise Identifier: I-2022-011-0011 Licensee: NextEra Energy Seabrook, LLC Facility: Seabrook Station Location: Seabrook, NH Inspection Dates: January 23, 2022 to February 10, 2022 Inspectors: C. Bickett, Senior Reactor Inspector P. Cataldo, Senior Reactor Inspector K. Mangan, Senior Reactor Inspector B. Pinson, Reactor Inspector M. Rossi, Resident Inspector A. Turilin, Reactor Inspector Approved By: Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Seabrook Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)
=
- (1) 480V BUS E62, 1-EDE-US-62
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance records, and corrective action history
- Equipment/environmental controls and qualification
- Adequacy of design (calculations and modifications)
- Surveillance testing and test results
- System and component level performance monitoring
- Equipment protection from fire, flood, steam, water intrusion, or spray
- Control logic
- Contactor and fuse ratings
- Component adequacy for minimum voltage
- Protection coordination (load in-rush and full load current)
- Range, accuracy, and setpoint of installed instrumentation
- Operator actions
- Process medium availability (electrical signal)
- Energy source availability (electricity)
The team used Appendix B guidance for Switchgear and Motor Control Centers.
- (2) Start-Up Feed Pump, 1-FW-P-113
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance records, and corrective action history
- Equipment/environmental controls and qualification
- Adequacy of design (calculations and modifications)
- Surveillance testing and test results
- System and component level performance monitoring
- Heat removal cooling water and ventilation
- Operator actions
- Process medium availability (water, air, electrical signal)
- Energy source availability (electricity, steam, fuel, air)
The team used Appendix B guidance for Pumps.
- (3) A Service Water Pump, P-41A
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance records, and corrective action history
- Adequacy of design (calculations and modifications)
- Surveillance testing and test results
- System and component level performance monitoring
- Equipment protection from fire, flood, steam, water intrusion, or spray
- Heat removal ventilation
- Control logic
- Component adequacy for minimum voltage
- Range, accuracy, and setpoint of installed instrumentation
- Operator actions
- Process medium availability (water)
- Energy source availability (electricity)
The team used Appendix B guidance for Pumps.
- (4) PCCW Train B Heat Exchanger, 1-CC-E-17-B
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Consistency among design and licensing bases and other documents/procedures
- Adequacy of design (calculations and modifications)
- System and component level performance monitoring
- Heat removal cooling water and ventilation
- Process medium availability (water, air)
The team used Appendix B guidance for As Built Systems.
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)
- Energy source availability (electricity, steam, fuel, air)
- Operator Actions
- Normal, abnormal, and emergency operating procedures
- Control logic
- Component adequacy for minimum voltage
- Range, accuracy, and setpoint of installed instrumentation
- Adequacy of design (calculations and modifications
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- System health report, maintenance records, and corrective action history
- Consistency among design and licensing bases and other documents/procedures
- System and component level performance monitoring
- Surveillance testing and test results
- Equipment/environmental controls and qualification
- Heat removal cooling water and ventilation The team used Appendix B guidance for Electrical Motors, Fans, and EQ Splices/Maintenance/Surveillance Requirements.
Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)
- (2) EC 287967, Replacement Vital Battery 1B & 1D (Train B)
- (3) EC 295498, Containment Analysis Update for Heat Exchanger Calibration
- (6) EC 250048, Steam Generator Feed Pump Turbine Control Digital Upgrade
Review of Operating Experience Issues (IP Section 02.06) (2 Samples)
- (1) IN 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2
- (2) IN 2015-01, Degraded Ability to Mitigate Flooding Events
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 10, 2022, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Brian Booth, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21M Calculations 4.3.08-72F SW System Steady State Analysis Rev. 11
737-23 Startup Feedwater Pump NPSHA and Upstream Line Loses Rev. 2
9763-3-ED-00- Voltage Regulation Rev. 14
2-F
9763-3-ED-00- 480 V Coordination Rev. 04
31-F
C-S-1-20801 Emergency Feedwater System Flow Study Rev. 1
C-S-1-28002 Containment LOCA Response Using GOTHIC Rev. 3
C-S-1-28003 Containment MSLB Response Using GOTHIC Rev. 1
C-S-1-83618 Ocean and Cooling Tower Service Water Pump IST Rev. 9
Acceptance Criteria
C-X-1-21802 Expansion Joint Rupture in the Circulating Water System Rev. 3
Located in the Turbine Building
Corrective Action 02340882
Documents AR02418201
Corrective Action 02418427
Documents 02416980
Resulting from 02417001
Inspection 02417066
2417367
2417533
2417741
2418201
2418259
2418300
2418331
2418515
2418520
2418528
Drawings 1-CC-B20211 Primary Component Cooling Loop B Detail Rev. 22
1-DG-D20463 Diesel Generator Lube Oil System Train B Detail Rev. 18
1-FW-D20688 Emergency Feedwater System Details Rev. 20
Inspection Type Designation Description or Title Revision or
Procedure Date
Engineering EC 144952 DG Lube Oil Temperature Control Valve Modification 1-DG-V-29-
Changes A/B, Rev.
004
EC 250048 Steam Generator Feed Pump Turbine Digital Upgrade Rev. 12
Project
EC 287967 Replacement Vital Battery 1B & 1D (Train B) LTAM SEA 16- Rev. 004
0045
EC 291089 EFWPH Water In-Leakage Seal Repair Rev. 2
EC 295498 Containment Analysis Update for Heat Exchanger Rev. 0
Calibration
Engineering EE 90-10 Evaluation of Submerged Cables 03/09/1990
Evaluations EE-04-015 Response to NRC IR2004-003, Apparent Violation: DCR 97- Rev. 0
033 10 CFR 50.59 (Turbine Building Flood Protection)
EE-98-006 SW Pump Curves Rev. 000
Miscellaneous C-S-1-28009 Primary Containment Cooling Water System Heat Loads Rev. 0
and Flow Rates for Various Plant Operating Modes After
FP22285 Start-Up Feed Pumps Instructions Manual, Centrifugal Pump Rev. 0
FP57916 PCCW Heat Exchanger Instr Manual Rev. 000
FP700356 Failure Modes and Effects Analysis of the Seabrook Nuclear Rev. 0
Stations Steam Generator Feed Pump Turbine Digital
Control Upgrade Project - EC 250048
Procedures ES1850.017 SW Heat Exchanger Program Rev. 06
ON1090.13 Response to Natural Phenomena Affecting Plant Operations Rev. 24
OP-AA-109 Control of Time Critical Operator Actions and Time Sensitive Rev. 5
Actions
OS1238.02 Turbine Building Flooding Rev. 6
OS1246.02 Degraded Vital AC Power (Plant Operating) Rev. 25
OX1412.06 Monthly PCCW Loop B Valve Verification performed
2/08/22
OX1436.08 Startup Feed Pump Quarterly Surveillance Performed
10/25/21
OX1456.86 Operability Testing of IST Pumps Rev. 24
SM 7.20 Control of Time Critical Operator Actions and Time Sensitive Rev. 15
Inspection Type Designation Description or Title Revision or
Procedure Date
Actions
Work Orders 40577309
40405785-01
40405785-02
40405785-03
40508958
01195389
40638933
40725546
40079149-01
40632779-01
8