IR 05000443/2021010
| ML21106A063 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/20/2021 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Moul D Florida Power & Light Co, NextEra Energy Seabrook |
| References | |
| IR 2021010 | |
| Download: ML21106A063 (7) | |
Text
April 20, 2021
SUBJECT:
SEABROOK STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000443/2021010
Dear Mr. Moul:
On March 18, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station and discussed the results of this inspection with 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, X /RA/
Signed by: Melvin K. Gray
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-2021-010-0024
Licensee:
NextEra Energy Seabrook, LLC
Facility:
Seabrook Station
Location:
Seabrook, NH
Inspection Dates:
March 01, 2021 to March 18, 2021
Inspectors:
P. Cataldo, Senior Reactor Inspector
K. Mangan, Senior Reactor Inspector
A. Patel, Senior 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 (programs) 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), regional inspectors were directed to begin telework. Regional based inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. For the inspection documented below portions of the IP were completed remotely as well as on site and all the objectives and requirements for completion of the IP were met.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.cope b. Determined whether the sampled POVs are capable of performing their design-basis functions.
c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) RC-PCV-456-B, 'B' Power Operated Relief Valve
- (2) SWS-V-V4, Service Water to Secondary Component Cooling Isolation Valve
- (3) CBS-V-8, Containment Recirculation Sump Tank 101A Suction Isolation Valve
- (4) SI-V-139, Chemical and Volume Control/Safety Injection Cold Leg Isolation
- (5) RH-V-36, Residual Heat Removal Train 'B' Discharge to Safety Injection Suction Valve
- (6) SI-V-114, High Pressure Injection Common Cold Leg Discharge Motor Operated Valve
- (7) FW-V-156, Start-Up Feed Pump/Emergency Feed Water Cross Connect Isolation Valve
- (8) MS-V-395, Turbine Driven Emergency Feedwater Pump Common Steam Supply Isolation Valve
- (9) CC-TV-2171-1, Primary Component Cooling Water Heat Exchanger 'A' Outlet Flow Control Valve
- (10) MS-PV-3001, Steam Generator 'A' Atmospheric Relief Valve
- (11) CS-LCV-112-D, Reactor Water Storage Tank to Charging Pump Suction Isolation Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 18, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Brian Booth, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
C-S-1-80903
Motor Operated Valve Differential Pressure Calculation
09/25/1998
C-S-1-80904
Motor Operated Valve Trust, Actuator Capacity and
Torque Switch Setpoint Calculation
Rev. 4
C-S-1-91006
Adequacy of 1-MS-TK243 Air Capacity for 1-MS-V395
Revision 0
EE-03-005
AOV System Level Design Basis Review
Revision 0
Corrective Action
Documents
Resulting from
Inspection
2366952
2386027
2386030
2386031
2386982
2387155
Drawings
1-IA-B20644
Instrument Air Miscellaneous Building
Revision 18
Miscellaneous
73157
Composite Instruction Manual Valves & Actuators
Revision 0
97771
Instruction Manual for Kerotest Valves
Revision 9
Procedures
ES 1850 003
MOV Program Procedure
2/10/2004
ES1850.003
Motor Operated Valve Performance Monitoring
Rev. 18
ES1850.012
Air Operated Valve Program Procedure
Rev. 9
OX1436.02
Turbine Driven Emergency Feedwater Pump Quarterly
And Monthly Valve Alignment
Revision 32
STP-133
Stroke and Adjustment of MS-V393, MS-394, and MS-
V395
Revision 0
Work Orders
1134531
40625547