IR 05000335/2021002
| ML21222A151 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/10/2021 |
| From: | David Dumbacher NRC/RGN-II/DRP/RPB3 |
| To: | Coffey B Florida Power & Light Co |
| T Francis | |
| References | |
| IR 2021002 | |
| Download: ML21222A151 (14) | |
Text
August 10, 2021
SUBJECT:
ST LUCIE UNITS 1 & 2 - INTEGRATED INSPECTION REPORT 05000335/2021002 AND 05000389/2021002
Dear Mr. Coffey:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at St Lucie Units 1 & 2. On July 12, 2021, the NRC inspectors discussed the results of this inspection with Mr. Dan DeBoer, 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,
/RA/
David E. Dumbacher, Chief Reactor Projects Branch 3 Division of Reactor Projects
Docket Nos. 05000335 and 05000389 License Nos. DPR-67 and NPF-16
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000335 and 05000389
License Numbers:
Report Numbers:
05000335/2021002 and 05000389/2021002
Enterprise Identifier: I-2021-002-0012
Licensee:
Florida Power & Light Company
Facility:
St Lucie Units 1 & 2
Location:
Jensen Beach, FL 34957
Inspection Dates:
April 01, 2021 to June 30, 2021
Inspectors:
A. Butcavage, Reactor Inspector
B. Collins, Senior Reactor Inspector
T. Morrissey, Senior Construction Inspector
D. Orr, Senior Resident Inspector
S. Roberts, Resident Inspector
Approved By:
David E. Dumbacher, 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 St Lucie Units 1 & 2, 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
Type Issue Number Title Report Section Status LER 05000389/2021-001-00 Licensee Event Report, (LER) 05000389/2021-001-00, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center 71153 Closed
PLANT STATUS
Unit 1 operated at or near rated thermal power (RTP) until the unit was shut down on April 10, 2021 for a planned refueling outage. On May 17, 2021 the unit was restarted and returned to RTP on May 19, 2021. Unit 1 operated at or near RTP for the remainder of the inspection period.
Unit 2 operated at or near RTP for the entire inspection period.
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), resident and regional 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, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion 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 some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the licensee's readiness for seasonal extreme weather conditions prior to the onset of hurricane season, on May 30, 2021, for the following systems:
-Unit 1 and Unit 2 emergency diesel generator (EDG) systems
-Unit 1 and Unit 2 component cooling water (CCW) systems
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment were consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on May 3, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 alternate spent fuel cooling system during the Unit 1 outage, from April 20 - 22, 2021
- (2) Unit 1 'A' CCW train following system restoration on April 27, 2021 (3)2B low pressure safety injection (LPSI) pump due to a failed mechanical seal on the 2A LPSI pump on May 9, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 reactor coolant system safety injection tanks on April 30, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 1 reactor auxiliary building (RAB) 19.5' elevation on April 20, 2021
- (2) Unit 1 reactor containment building (RCB) on April 21, 2021
- (3) Unit 2 'B' train emergency core cooling system (ECCS) rooms for LPSI, high pressure safety injection (HPSI), and containment spray (CS) on May 11, 2021
- (4) Unit 2 RAB 62' elevation on June 1, 2021
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 19, 2021 to April 27, 2021
03.01.a - Nondestructive Examination and Welding Activities.(Reviewed)
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- None Scheduled
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- AR 02389475, Minor BA Corrosion on Valve 02360, Isolation Valve
- AR 02331828, Pressure Transmitter, PT-1182,
- WR 94200279, PT-1182, RCP-1B2 Upper Seal Cavity, Evaluation
- WO 40687628, Valve 02360 - Disassemble, Inspect and Repair
- WO 40696530, SL1-30 RCB BACC List (Initial Containment Walkdown)
Reviewed
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- SG A, tubes R64C11, R101C74, and R125C68, ASME Class 1 (observed via screen share)
- SG B, tubes R123C94, R137C78, and R139C92, ASME Class 1 (observed via screen share)
Operating Experience Review:
- Review of St Lucie Disposition of NSAL 20-1 issued for the Part 21 by Westinghouse
- St. Lucie 1, Risk Informed Program Review / Discussion with Program Owner
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 in the control room during:
- A planned power reduction and shutdown of Unit 1 to support a refueling outage on April 9 - 10, 2021
- Unit 1 startup and power ascension activities following a refueling outage on May 17 - 18, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) On June 7, 2021, the inspectors observed a licensed operator continuing training evaluation in the control room simulator. The simulated scenario included multiple dropped rods, manual reactor trip, inadvertent actuation of emergency features activation system (ESFAS), and a small break loss of coolant accident (SBLOCA).
The SBLOCA resulted in an Emergency Plan Alert classification which required a simulated notification to the local counties and State of Florida authorities and the NRC.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Action Request (AR) 2381327 2B charging pump failed to start, on June 29, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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) Unit 1 yellow shutdown safety assessment (SSA) with the reactor coolant system (RCS) depressurized and level lowered to support reactor head removal from April 12
- 14, 2021
- (2) Unit 2 elevated risk with the 2A startup transformer out of service (OOS) for planned maintenance from April 19 - 22, 2021
- (3) Unit 1 yellow SSA with the RCS depressurized and level lowered to support reactor head installation from May 1 - 3, 2021
- (5) Unit 1 yellow shutdown SSA with the RCS depressurized and level lowered to support reactor coolant pump (RCP) 1B1 and 1B2 seal replacements on May 12, 2021
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) AR 2390041, Unit 1 containment cooler, HVS-1B, CCW piping support degradation on May 3, 2021
- (2) AR 2392883, 2C auxiliary feedwater (AFW) pump small oil leak from equalizer pipe on May 13, 2021
- (3) AR 2394536, Unit 1 annunciator H-6 reactor seal pressure high received on May 29, 2021
- (4) AR 2394479, Part 21 Report for Siemens 5-DPU-350-1200-78 MV Vacuum Breakers issued on June 3, 2021
- (5) AR 2395670, Unable to perform 1C CCW pump comprehensive flow test on June 23, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
- (1) Engineering Change 294435 1A3/1B3 4 kV SWGR replace SF6 breakers with vacuum breakers
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Work order (WO) 40696099, Unit 1 CCW heat exchanger clean, inspect, and tube replacement on April 27, 2021
- (2) WO 40711550, 1A LPSI suction check valve elbow replacement on May 3, 2021
- (3) WO 40601118, 1C AFW pump governor replacement on May 6, 2021
- (4) WO 40718309, 2A LPSI pump code run failure on May 17, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 1 refueling outage (SL1-30) activities from April 10 through May 17, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)1-SMM-08.08, " Main Steam Safety Valve Setpoint Surveillance using Furmanite Trevitest Mark VIII-2 Equipment" on April 9, 2021 (2)1-OSP-69.13A, "ESF-Staggered 36-month surveillance for SIAS/CIS/CSAS - Train A" from April 10 - 12, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
(1)1-OSP-68.02, "Local Leak Rate Test," (Section 4.14, Penetration 28B, RCS hot leg sample) on April 22, 2021
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) On June 7, 2021, the inspectors observed a licensed operator continuing training evaluation in the control room simulator that included an Emergency Plan Alert classification which required a simulated notification to the local counties and State of Florida authorities and the NRC.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1, April 1, 2020 through March 31, 2021
- (2) Unit 2, April 1, 2020 through March 31, 2021
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1, April 1, 2020 through March 31, 2021
- (2) Unit 2, April 1, 2020 through March 31, 2021
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program (CAP) for potential adverse trends that might be indicative of a more significant safety issue. The inspectors concluded there was no adverse trend.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000389/2021-001-00, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center (ADAMS Accession Number ML21069A341). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 12, 2021, the inspectors presented the integrated inspection results to Mr. Dan DeBoer, Site Vice President, and other members of the licensee staff.
- On April 30, 2021, the inspectors presented the Results of St. Lucie Unit-1, ISI & SG Inservice Inspection results to Mr. Dan DeBoer, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.08P Corrective Action
Documents
Future Reactor Internals Inspections, 2027
March 12,
21
Boric Acid Leak was observed on the Unit 1 PT-1182
Pressure Transmitter and Support Bracket
October 17,
2019
Engineering
Evaluations
AIM 201110885-
Intertek Degradation Assessment for St. Lucie Unit 1 Steam
Generators for End-of-Cycle 29 (Spring 2021 Outage)
Rev. 0
Miscellaneous
Framatome Certificate of Personnel Qualification: ET III-QDA
(Washburn)
July 5, 2019
Framatome Certificate of Vision Examination (Washburn)
January 5,
21
Framatome Certificate of Personnel Qualification: ET III-QDA
(Brooks-Crocker)
May 7, 2020
Framatome Certificate of Vision Examination (Brooks-
Crocker)
January 5,
21
Curtiss-Wright Personnel Certification Summary Record: ET
II (Hamilton)
September
10, 2018
Curtiss-Wright Vision Examination Certification (Hamilton)
March 5,
21
AREVA Delta SAP Expansion Result (Tube Plug Record:
SG1B R121C92)
April 24,
21
AREVA Delta SAP Expansion Result (Tube Plug Record:
SG1A R126C83)
April 24,
21
LMT-SOP-46
Personnel Certification Statement, Fish, E,,(2/5/21),
Rogotzke,
- J. (1/27/21), Coburn,
- T. (2/5/21), Thompson B.
(4/1/21), DiValerio, P (12/21/20)
Rev. 7
EPID L-2019-
LLR-0044
S
- T. LUCIE PLANT, UNIT NO. 1 - SAFETY EVALUATION
FOR RELIEF REQUEST FOR FIFTH TEN-YEAR
INSERVICE INSPECTION INTERVAL - ALTERNATIVE
RISK-INFORMED INSERVICE INSPECTION PROGRAM
FOR CLASS 1 AND 2 PIPING WELDS
June 25,
20
IOC-CSl-NDE-21
-009
Training Documentation for "Computer Based NDE Training
for Thermal Fatigue Cracking"
March 17,
21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(MRP-36, Revision 4).
T. Coburn
Krautkramer
Model USN 60
SW, SN-022PPL
Ultrasonic Instrument Calibration Data Record and
Certification
January 5,
21
Welder ID: LPHA
Welder Qualification
Exp. October
5, 2021
WPS-140
Welding Procedure Spec. GTAW - Manual, Carbon Steel
Rev. 0
WPS-43
Welding Procedure Spec., GTAW - Manual, Stainless Steel
Rev. 12
NDE Reports
51-9263907-000
AREVA Inc. Engineering Information Record: St. Lucie Unit 1
SL1-27 Secondary Side Inspection Final Report
Rev. 000
51-9284171-000
Framatome Inc. Engineering Information Record: Secondary
Side Visual Inspection Final Report for FPL, St. Lucie 1-28
Rev. 000
Line SI-511/Joint
2000
WO# 40711550, Radiographic Inspection Report,
April 26,
21
Report No. PSL1-
UT-21-012
Summary No. SL 1-083505, Augmented MRP146, Elbow to
April 23,
21
Report No.: PSL
1-VT-21-060
Component ID: 51-676-2076, Strut Support, Pre-Service
Inspection
April 26,
21
Rpt. No. PSL 1-
UT-21-008
Summary No. SL 1-027300UT, Comp ID RC-121-3-503,
Elbow to Pipe
April 20,
21
Rpt. No. PSL 1-
VT-21-037
Visual Examination of Support (VT-3), RV Support@ 60° (A1
Cold leg)
April 26,
21
Rpt. No. PSL1 -
UT-21 -012
Summary No. SL 1-083505, Elbow to Pipe Weld, Augment
April 23,
21
Rpt. No. PSL1-
UT-21-003
Summary No. SL1-023520, UT, Elbow to Safe-End, RC-123-
FW-2000
April 23,
21
Rpt. No.: PSL 1-
UT-21-009
Summary No.: SL 1-027600, Comp ID RC-121-FW-2-500B,
Pipe to Elbow
April 20,
21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Rpt. No.: PSL1-
VT-21-004
Summary No.: SL1-026170, Compt. ID: 510-01-12, Cold
April 16,
21
Procedures
03-1275284
Framatome Field Procedure for Remote Rolled Plugging
Utilizing Plugging Control Box
Rev. 024
03-9324514
Framatome Secondary Side Visual Inspection Plan and
Procedure for FPL, St. Lucie 1-30
Rev. 000
54-ISI-24-038
Framatome Inc. NDE Administrative Procedure: Written
Practice for Personnel Qualification in Eddy Current
Examination
Rev. 038
54-ISI-400-024
Framatome Inc. Nondestructive Examination Procedure:
Multi-Frequency Eddy Current Examination of Tubing
Rev. 024
ETSS_1_R0
Framatome Examination Technique Specification Sheet
(Bobbin)
Rev. 0
ETSS_2_R0
Framatome Examination Technique Specification Sheet (3-
coil +Pt)
Rev. 0
ETSS_3_R0
Framatome Examination Technique Specification Sheet (1-
coil +Pt)
Rev. 0
ETSS_4_R0
Framatome Examination Technique Specification Sheet
(Xprobe)
Rev. 0
NDE 4.15
Visual Examination (VE), ASME Section XI Code Case N-
2-1, N-729-4, N-770-2 and
Bare Metal Visuals
February 27,
2019
NDE 5.2
Component Support & Inspection, Ultrasonic Examination of
Ferritic Piping Welds
August 27,
2018
NDE 5.32
Ultrasonic Examination Technique Austenitic Piping Welds
For Thermal Fatigue Cracking/Crazing (MRP-146 & MRP-
2)
March 17,
21
Work Orders
Weld Traveler 02000-022619
April 26,
21