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, 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:
Report Number:
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
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
Procedure
Type
Designation
Description or Title
Revision or
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-
2-F
Voltage Regulation
Rev. 14
9763-3-ED-00-
31-F
480 V Coordination
Rev. 04
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
Acceptance Criteria
Rev. 9
C-X-1-21802
Expansion Joint Rupture in the Circulating Water System
Located in the Turbine Building
Rev. 3
Corrective Action
Documents
2340882
Corrective Action
Documents
Resulting from
Inspection
2418427
2416980
2417001
2417066
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
DG Lube Oil Temperature Control Valve Modification
1-DG-V-29-
A/B, Rev.
004
Steam Generator Feed Pump Turbine Digital Upgrade
Project
Rev. 12
Replacement Vital Battery 1B & 1D (Train B) LTAM SEA 16-
0045
Rev. 004
EFWPH Water In-Leakage Seal Repair
Rev. 2
Containment Analysis Update for Heat Exchanger
Calibration
Rev. 0
Engineering
Evaluations
EE 90-10
Evaluation of Submerged Cables
03/09/1990
EE-04-015
Response to NRC IR2004-003, Apparent Violation: DCR 97-
033 10 CFR 50.59 (Turbine Building Flood Protection)
Rev. 0
EE-98-006
SW Pump Curves
Rev. 000
Miscellaneous
C-S-1-28009
Primary Containment Cooling Water System Heat Loads
and Flow Rates for Various Plant Operating Modes After
Rev. 0
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
Stations Steam Generator Feed Pump Turbine Digital
Control Upgrade Project - EC 250048
Rev. 0
Procedures
ES1850.017
SW Heat Exchanger Program
Rev. 06
ON1090.13
Response to Natural Phenomena Affecting Plant Operations
Rev. 24
Control of Time Critical Operator Actions and Time Sensitive
Actions
Rev. 5
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Actions
Work Orders
40577309
40405785-01
40405785-02
40405785-03
40508958
01195389
40638933
40725546
40079149-01
40632779-01