IR 05000335/2019002
| ML19210C251 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/25/2019 |
| From: | Randy Musser NRC/RGN-II, Division Reactor Projects II |
| To: | Moul D Florida Power & Light Co |
| Reeder D | |
| References | |
| IR 2019002 | |
| Download: ML19210C251 (11) | |
Text
July 25, 2019
SUBJECT:
SAINT LUCIE UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000335/2019002 AND 05000389/2019002
Dear Mr. Moul:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Saint Lucie Units 1 and 2. On July 25, 2019, the NRC inspectors discussed the results of this inspection with Mr. DeBoer and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Randall A. Musser, 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:
05000335/2019002 and 05000389/2019002
Enterprise Identifier: I-2019-002-0018
Licensee:
Florida Power & Light Company
Facility:
Saint Lucie Units 1 and 2
Location:
Jensen Beach, FL 34957
Inspection Dates:
April 01, 2019 to June 30, 2019
Inspectors:
T. Morrissey, Senior Resident Inspector
S. Roberts, Resident Inspector
A. Wilson, Project Engineer
Approved By:
Randall A. Musser, 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 Saint Lucie Units 1 and 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 2019-001-00 for St.
Lucie, Unit 1, Automatic Reactor Trip Caused by Main
Generator Ground Resulting
in Generator Lockout/Loss of
Load
Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On April 25, 2019 the unit
automatically tripped from RTP due to a main generator ground and associated generator
lockout. On May 9, 2019, the unit was cooled down to Mode 5 (< 200oF). The ground condition
was repaired and the unit was restarted on June 20, 2019 and reached RTP on June 22, 2019.
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 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Summer Readiness Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated summer readiness of offsite and alternate alternating
current (AC) power systems on May 30, 2019.
Seasonal Extreme Weather Sample (IP Section 03.02) (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, 2019.
External Flooding Sample (IP Section 03.04) (1 Sample)
(1)
The inspectors evaluated the licensee's readiness to cope with external flooding on
May 30, 2019.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1)
Unit 2, 2A and 2C charging pumps while the 2B charging pump was out of service
(OOS) for maintenance, on April 23, 2019
(2)
Unit 2, 2B high pressure safety injection (HPSI) train, while the 2A HPSI train was
OOS for planned maintenance, on May 6, 2019
(3)
Unit 1, 1B emergency diesel generator (EDG), while the 1A EDG was OOS for
planned maintenance, on May 14, 2019
(4)
Unit 2, 2A emergency core cooling system (ECCS) train while the 2B ECCS train was
OOS for a weld repair associated with a socket weld of V07332 (bypass valve for 2B
containment spray pump discharge valve), on May 29, 2019
(5)
Unit 1, 1B component cooling water (CCW) train while the 1A CCW heat exchanger
(HX) was OOS for planned maintenance, on May 30, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the
Unit 2 HPSI system on April 17, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (6 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1)
Unit 1, 1B switchgear room, on April 1, 2019
(2)
Unit 1, 1A ECCS area, reactor auxiliary building (RAB), -10 foot (ft) elevation, on
April 28, 2019
(3)
Unit 1, CCW system area, on May 8, 2019
(4)
Unit 2, 2B switchgear room, on June 14, 2019
(5)
Unit 2, A and B vital battery rooms, on June 26, 2019
(6)
Unit 1, RAB -0.5 ft elevation, on June 27, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of the:
(1)
1A CCW HX by verifying periodic maintenance was in accordance with Electric Power
Research Institute (EPRI) HX performance monitoring guideline, NP-7552, on
May 27 - 30, 2019.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (3 Samples)
(1)
On April 11, 2019, the inspectors observed licensed operator performance in the
control rooms, for both Unit 1 and Unit 2, during operations surveillance procedure
0-OSP-53.01, Reactive Power Lagging Capability Test.
(2)
On May 9, 2019, the inspectors observed licensed operator performance in the Unit 1
control room when cooling down the plant from normal operating temperature to
Mode 5 in accordance with general operating procedure 1-GOP-305, Reactor Plant
Cooldown - Hot Standby to Cold Shutdown.
(3)
On June 20-21, 2019, the inspectors observed licensed operator performance in the
Unit 1 control room during power ascension from one percent thermal power to 45
percent thermal power in accordance with general operating procedure 1-GOP-201,
Reactor Plant Startup - Mode 2 to Mode 1.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
On April 4, 2019, the inspectors observed a simulator-based licensed operator
requalification training emergency plan evaluation on the control room simulator. The
simulated scenario included a steam generator tube leak, a manual reactor trip, and
the steam generator tube leak degrading into a tube rupture. The degradation of the
reactor coolant system boundary resulted in an Alert emergency classification which
required a simulated notification to the State of Florida and the NRC.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with
the following equipment and/or safety significant functions:
(1)
Unit 2, action request (AR) 2311852, ground on HVS-1B containment fan cooler, on
April 23, 2019
(2)
Unit 1, EDG system, system health report, dated May 6, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work
activities:
(1)
Unit 2, elevated risk with 2B charging pump OOS for planned maintenance and
containment cooler HSV-1B OOS due to a motor ground, on April 23, 2019
(2)
Unit 2, elevated risk with 2A containment spray (CS) pump and 2A low pressure
safety injection (LPSI) pump OOS for planned maintenance, on May 8, 2019
(3)
Unit 1, shutdown risk assessment with 1B intake cooling water (ICW) header OOS to
support removal of the 1B CCW HX for planned maintenance, on May 10, 2019
(4)
Unit 1, elevated risk with the 1A EDG OOS for planned maintenance, from
May 13-14, 2019
(5)
Unit 1, elevated risk with the 1A CCW HX OOS for planned maintenance, on
May 28, 2019
(6)
Unit 2, elevated risk with the 2B ECCS train OOS for an emergent weld repair of a
socket weld for V07332 (bypass valve for 2B containment spray pump discharge
valve), on May 29, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (5 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1)
Unit 2, AR 2308656, B hot leg injection check valve, V3526, seat leakage, on
April 16, 2019
(2)
Unit 2, ARs 2310862, 2311010, pipe clamps missing on CCW piping to radiation
monitors RM-26-1 and RM-26-2, on April 19, 2019
(3)
Unit 2, AR 2306232, 2C charging pump breaker-wrong sensor tab and settings
found, on April 22, 2019
(4)
Unit 1, AR 2317351, 1A1 safety injection header check valve (V3227) seat leakage,
on June 13, 2019
(5)
Unit 1, AR 2312829, Unit 1 control room heating, ventilation, and air conditioning
(HVAC) door needing repair, on June 25, 2019
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 or permanent modifications:
(1)
Unit 2, engineering change (EC) 293128, containment fan cooler 2-HVS-1B fast
speed coil bypass, on April 29, 2019.
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance tests:
(1)
Unit 2, work order (WO) 40594978, MV-09-13, auxiliary feed water (AFW) 2A and 2B
discharge, switch replacement, on April 8, 2019
(2)
Unit 1, WO 40660796, replace refueling water tank (RWT) level transmitter,
LT-07-2D, power supply on April 22, 2019
(3)
Unit 1, WO 40664017, calibrate and replace 1A EDG temperature switch
TS-59-003A, on May 15, 2019
(4)
Unit 2, WO 40614974, V3659, safety injection header A isolation valve (minimum
flow) maintenance, on May 20, 2019
(5)
Unit 2, WO 40283289, control element assembly (CEA) subgroup 18 power supply
replacement, on May 21, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
Unit 1 Forced Outage (April 25 - June 21, 2019)
On April 25, 2019, St. Lucie Unit 1 was in Mode 1 at 100 percent reactor power.
At 0918 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.49299e-4 months <br /> the reactor tripped due to a generator lockout during reactive power
lagging capability testing when the generator backup ground protection relay tripped.
Automatic turbine and reactor trips occurred in response to the lockout as expected.
An event investigation determined that the direct cause of the generator ground
resulted from failure of the ground wall insulation in the stator winding. The
inspectors evaluated Unit 1 forced outage activities from April 25, 2019 until the unit
was returned to service on June 21, 2019. The inspectors completed applicable
portions of sections 03.01a, 03.01b, 03.01, 03.01d-1, and 03.01e-1 of IP 71111.20.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Inservice Testing (IP Section 03.01) (1 Sample)
(1)
Unit 2, 2-OSP-21.01C, "2C Intake Cooling Water Pump Code Run," on May 16, 2019
Surveillance Tests (other) (IP Section 03.01) (3 Samples)
(1)
Unit 1, 1-SMI-69.02, "Engineered Safeguards Actuation System - Channel Functional
Test," on April 8, 2019
(2)
Unit 1, 1-OSP-63.01, "RPS Logic Matrix Test," on April 26, 2019
(3)
Unit 1, 1-OSP-69.14A, ESF - 18 Month Surveillance for EDG Start on SIAS Without
LOOP and 24-Hour Load Run - Train A, on May 13-14, 2019
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) (2 Samples)
(1)
Unit 1 (April 1, 2018, through March 31, 2019)
(2)
Unit 2 (April 1, 2018, through March 31, 2019)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
(1)
Unit 1 (April 1, 2018, through March 31, 2019)
(2)
Unit 2 (April 1, 2018, through March 31, 2019)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program for potential
adverse trends that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issue:
(1)
AR 2307010, SE-59-1A1, (2A EDG day tank fill valve) leaks by, on June 24, 2019.
This issue was selected due to its impact to the operability of the 2A EDG.
71153 - Followup of Events and Notices of Enforcement Discretion
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs) which can be
accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
(1)
LER 05000335/2019-001-00, Automatic Reactor Trip Caused by Main Generator
Ground Resulting in Generator Lockout/Loss of Load. 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 also concluded
that no violation of NRC requirements occurred. This LER is closed.
Personnel Performance (IP Section 03.03) (1 Sample)
(1)
On April 25, 2019 at 0918 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.49299e-4 months <br />, St. Lucie Unit 1 experienced a reactor trip due to a
loss of load from a turbine trip. The inspectors reviewed operator performance in
response to the trip, operator logs, computer and recorder data, and the post trip
report to verify plant equipment, and operations personnel, responded appropriately.
The inspectors provided details regarding operator and equipment performance to
NRC management. The licensee determined that a ground developed on the
generator stator and protective relays initiated the turbine trip. The inspectors verified
the cause of the trip was appropriately resolved prior to unit restart. The unit was
restarted on June 20, 2019 and was returned to RTP on June 22, 2019. Related LER 05000335/2019-001-00, is closed above.
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 Sample)
(1)
The inspectors evaluated the licensees independent spent fuel storage installation
cask loading of Unit 1 dry shielded cask (DSC)-088, during the week of
March 31, 2019 and Unit 2 DCS-094, during the week of May 19, 2019. Specifically,
the inspectors observed/reviewed the following activities:
- Fuel selection and fuel loading
Heavy load movement of DSC-088 and DCS-094
Drying and backfill evolutions
Closure welding and non-destructive weld evaluations
Transfer and transport evolutions
Radiological field surveys
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 25, 2019, the inspectors presented the integrated inspection results to Mr.
DeBoer and other members of the licensee staff.