IR 05000443/2020001
| ML20119B066 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 04/29/2020 |
| From: | Brice Bickett NRC Region 1 |
| To: | Moul D Florida Power & Light Co |
| References | |
| IR 2020001 | |
| Download: ML20119B066 (10) | |
Text
April 29, 2020
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - INTEGRATED INSPECTION REPORT 05000443/2020001 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) REPORT NO. 07200063/2020001
Dear Mr. Moul:
On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station, Unit No. 1. On April 17, 2020, the NRC inspectors discussed the results of this inspection with Mr. Eric McCartney, 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: NRC-PIV
Brice A. Bickett, Chief Reactor Projects Branch 3 Division of Reactor Projects
Docket No. 05000443 and 07200063 License No. NPF-86
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000443 and 07200063
License Number:
Report Number:
05000443/2020001 and 07200063/2020001
Enterprise Identifier: I-2020-001-0025 and I-2020-001-015
Licensee:
NextEra Energy Seabrook, LLC
Facility:
Seabrook Station, Unit No. 1
Location:
Seabrook, NH
Inspection Dates:
January 01, 2020 to March 31, 2020
Inspectors:
P. Cataldo, Senior Resident Inspector
T. Daun, Resident Inspector
N. Floyd, Senior Reactor Inspector
O. Masnyk Bailey, Health Physicist
Approved By:
Brice A. Bickett, Chief
Reactor Projects Branch 3
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Seabrook Station, Unit No. 1, 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.
PLANT STATUS
Seabrook Station began the inspection period operating at 100 percent rated thermal power and on March 31, 2020, operators commenced a shutdown, from 96 percent power, for planned refueling and maintenance outage 20 (RFO20) that commenced on April 1,
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 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. From January 1 - March 19, 2020, the inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week and conducted plant status activities as described in IMC 2515, Appendix D, and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather on February 13
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'B' train containment building spray system while 'A' train containment building spray system was out-of-service for planned maintenance on January 14 (2)
'A' emergency diesel generator while 'B' emergency diesel generator was out-of-service for maintenance on January 28
- (3) Return-to-service following startup feed pump operability surveillance on February 19
- (4) Motor-driven emergency feedwater pump during steam-driven emergency feedwater pump testing on March 19
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Primary auxiliary building piping penetration area, PP-1A-Z, on March 19
- (2) Primary auxiliary building piping penetration area, PP-1B-Z, on March 19
- (3) Primary auxiliary building piping penetration area, PP-2A-Z, on March 19
- (4) Primary auxiliary building piping penetration area, PP-2B-Z, on March 19
- (5) Primary auxiliary building piping penetration area, PP-3B-Z, on March 19
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on March 12
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Primary auxiliary building 7 elevation on March 27
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance of the following activities in the control room:
- Plant computer swap over on March 6
- Plant and reactor shutdown for entry into refueling outage 20 on March 31
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification training in the simulator on February 25
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Main plant computer system upgrade project and impacts on maintenance rule functions associated with the reactor coolant system and primary containment parameters on March 30
- (2) Emergency feedwater pump room scaffolding installation deficiencies and corrective actions during the week of March 23
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Elevated risk during 'A' vital battery return-to-service on January 6
- (2) Elevated risk during service water maintenance window on January 15 (3)
'B' battery testing and 'B' emergency diesel generator out-of-service on January 28 (4)
'B' and 'D' battery cross-connect activities and 'B' charging pump maintenance on January 29
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Primary component cooling water temperature controller and associated temperature control valve on January 7
- (2) Control rod drive mechanism thermal sleeve prompt operability determination that was formalized on January 10
- (3) Incorrect flowmeter used for data collection during charging pump surveillance on March 5
- (4) Poly-acrylic acid injection impact on volumetric flow instrumentation and Technical Specification compliance during the week of March 9
- (5) Alkili-Silica reaction structural loading calculations affecting seismic design criterion requirements for the emergency feedwater and service water cooling tower buildings in March 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary modification:
- (1) Power range neutron flux reactor protection system setpoint power change for shutdown activities on March 11
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Station battery charger following capacitor and control board replacement on January 9
- (2) Thermal overload relay replacement for CBS-V2 on January 14 (3)
'A' control building air handling system following heating element replacement on January 15
- (4) Mechanical interlock corrective maintenance for battery bus 11B normal supply breaker conducted on January 29 (5)
'B' emergency diesel generator troubleshooting activities and corrective maintenance on January 28
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Main turbine auto-stop pressure switch calibration on January 16
- (2) Startup feedpump quarterly surveillance on January 21 (3)
'B' reactor coolant pump under-frequency and under-voltage quarterly surveillances on January 23
- (4) Motor-driven emergency feedwater in-service testing of piping on February 20
- (5) Steam-driven emergency feedwater surveillance on March 19
Inservice Testing (IP Section 03.01) (1 Sample)
(1) 'B' residual heat removal flow and valve stroke test on February 26
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the conduct of a routine, full participation emergency planning drill on March
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) For the period January 1, 2019 through December 31, 2019
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) For the period January 1, 2019 through December 31, 2019
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) For the period January 1, 2019 through December 31,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants
- (1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation
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 9, 2020, the inspectors presented the Independent Spent Fuel Storage Installation inspection results to Mr. Eric McCartney, Site Vice President and other members of the licensee staff.
- On April 17, 2020, the inspectors presented the Integrated Inspection results to Mr. Eric McCartney, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60855.1
Procedures
FX3000.15
DFS Contingency Plans
Revision 4
NF-AA100-1000
Special Nuclear Material Control and Accountability
Revision 6
RPT SBK-19-003
Independent Spent Fuel Storage Installation
05/04/2019
RS00720
SNM Inventory Control
Revision 20