IR 05000335/2018004

Nuclear Regulatory Commission Integrated Inspection Report 05000335/2018004 and 05000389/2018004

ML19023A260
Person / Time
Site:	Saint Lucie
Issue date:	01/23/2019
From:	Randy Musser NRC/RGN-II/DRP/RPB3
To:	Nazar M Florida Power & Light Co
Geanette D
References
IR 2018004
Download: ML19023A260 (14)

Text

UNITED STATES January 23, 2019

SUBJECT:

ST. LUCIE PLANT - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000335/2018004 AND 05000389/2018004

Dear Mr. Nazar:

On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your St. Lucie Plant Units 1 and 2. On January 10, 2019, the NRC inspectors discussed the results of this inspection with Mr. Coffey 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. 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 Porjects Docket Nos.: 50-335, 50-389 License Nos.: DPR-67, NPF-16

Enclosure:

IR 05000335/2018004 and 05000389/2018004

REGION II==

Docket Nos: 50-335, 50-389 License Nos: DPR-67, NPF-16 Report Nos: 05000335/2018004, 05000389/2018004 Enterprise Identifier: I-2018-004-0048 Licensee: Florida Power & Light Company (FPL)

Facility: St. Lucie Plant, Units 1 and 2 Location: 6501 South Ocean Drive Jensen Beach, FL 34957 Dates: October 1, 2018 through December 31, 2018 Inspectors: T. Morrissey, Senior Resident Inspector S. Roberts, Resident Inspector P. Capehart, Senior Operations Engineer (Section 71111.11)

Approved by: R. Musser, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a baseline inspection at St. Lucie Plant 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 None Additional Tracking Items Type Tracking number Title Report Section Status Licensee 05000389/2018-002-00 Automatic Reactor 71153 Closed Event Trip Due to a Report Breaker Failure on (LER) the 2A1 6.9 kV Bus

PLANT STATUS

Unit 1 began the inspection period at rated thermal power (RTP). On October 29, 2018, the unit was manually tripped from RTP when steam generator levels could not be maintained due to 4B low pressure feedwater heater level control system problems. The unit was restarted on October 30, 2018 and the 4B feedwater heater level control system was repaired. The unit was returned to RTP on November 1, 2018. On November 29, 2018, unit power was reduced to approximately 90 percent RTP in order to repair a normal level control valve for a moisture separator reheater. The unit was returned to RTP that same day. The unit was at or near RTP for the remainder of the inspection period.

Unit 2 began the inspection period shutdown at normal operating pressure and temperature following a planned refueling outage. The unit was restarted on October 2, 2018 and was returned to RTP power on October 5, 2018. On October 12, 2018, the unit experienced an automatic reactor trip from RTP due to a fault on the non-safety 2A1 6.9 kV (kilovolt) bus during a transfer of the bus power supply from the 2A auxiliary transformer to the 2A startup transformer (SUT). The fault caused a fire in the 2A auxiliary transformer feeder breaker that was extinguished by the onsite fire brigade. The 2A1 bus was repaired with the exception of the 2A auxiliary transformer feeder breaker cubicle. The 2A1 6.9 kV bus was energized from the 2A SUT. The unit was restarted on October 17, 2018 and was returned to RTP on October 18, 2018. On December 15, 2018, the licensee conducted a rapid down power to 90 percent due to the 2A heater drain pump tripping on low level that was a result of a failure of the 5A heater level control valve. The level control valve solenoid was replaced and on December 16, 2018, the unit was returned to RTP. The unit was at or near RTP for the remainder of the 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.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather

The inspectors evaluated and completed a review of the licensees readiness for seasonal winter weather conditions from November 14-15, 2018.

71111.04 - Equipment Alignment Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2, 2A emergency diesel generator (EDG) train with 2B EDG out of service (OOS) for emergent work, on October 5, 2018

(2) Unit 1, 1B high pressure safety injection (HPSI) train, while 1A HPSI train was OOS for planned maintenance, on November 20, 2018

(3) Unit 2, 2A component cooling water (CCW) train while 2B CCW train OOS for planned maintenance, on November 28, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the Unit 2 charging system, on November 5, 2018.

71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 2, EDG building, on October 22, 2018

(2) Unit 1, reactor auxiliary building (RAB) 19.5 foot elevation north-south hallway, on November 1, 2018

(3) Unit 2, intake cooling water (ICW) building, on November 9, 2018

(4) Unit 2, RAB -0.5 foot elevation, on December 12, 2018

(5) Unit 1, RAB 43 foot elevation, ventilation room, on December 18, 2018

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

On October 17, 2018, the inspectors observed and evaluated a licensed operator crew during an annual exam on the control room simulator. The simulated scenario included a steam generator tube leak that degraded to a steam generator tube rupture requiring a rapid down power. The steam generator tube rupture condition resulted in an Alert emergency classification which required a notification to the State of Florida and the NRC.

Operator Performance (2 Samples)

(1) The inspectors observed and evaluated operator performance during Unit 2 startup and power ascension after a planned refueling outage, on October 3, 2018

(2) The inspectors observed and evaluated operator performance during Unit 2 startup and power ascension after a forced outage, on October 17, 2018

Operator Exams (1 Sample)

The inspectors performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations that were completed on December 20, 2018.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following risk significant system:

Unit 2 auxiliary feedwater (AFW) system

71111.13 - Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Unit 2, elevated green risk associated with 2B EDG out of service for emergent work and 2B charging pump out of service for planned maintenance, on October 5, 2018

(2) Unit 2, elevated green risk assessment with the unit shutdown in Mode 3 while repairing non-safety related 2A1 6.9 kV bus that was damaged from an electrical fault, on October 12, 2018

(3) Unit 2, elevated green risk assessment with the 2A HPSI pump, 2A low pressure safety injection (LPSI) pump, and valve HCV-3647 HPSI Header A to Loop 2B2 out of service for planned maintenance, on November 5, 2018

(4) Unit 2, elevated green risk assessment with the 2B CCW heat exchanger (HX) out of service for planned maintenance, on November 27-29, 2018

(5) Unit 1 and Unit 2, elevated green risk assessment with the 1B and 2B startup transformers out of service for planned maintenance, on November 30, 2018

(6) Unit 1, elevated green risk assessment with the 1B HPSI, 1B LPSI, and 1B containment spray pump out of service for planned maintenance and surveillance testing on December 19, 2018

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 2, Action Request (AR) 2285014, significant corrosion on valve bonnet and cap screws, 2C AFW pump discharge valve V09140, on October 23, 2018

(2) Unit 1, ARs 2286219, 2286220, multiple battery cells have cracks in top cover (1A and 1B 125V battery banks), on October 24, 2018

(3) Unit 2, AR 2284898, V2554 (charging pump 2B discharge recirculation valve) not meeting stroke time, on October 24, 2018

(4) Unit 1, AR 2285372, refueling water tank (RWT) to charging system piping not designed as seismic piping, on November 1, 2018

(5) Unit 2, AR 2289612, emergency core cooling system exhaust fan HVE-9A failed surveillance, on November 6, 2018

(6) Unit 1, AR 2271392, steam generator 1A water level narrow range deviation, on November 7, 2018

71111.18 - Plant Modifications

The inspectors evaluated the following permanent modification:

Engineering change (EC) 292235, Install vent valve V03996 on 1A HPSI pump suction pipe

71111.19 - Post Maintenance Testing

The inspectors evaluated the following post-maintenance tests:

(1) Unit 2, Work Order (WO) 40580504, B Train Quarterly Non Check Valve Cycle Test, following repair of V2254 (charging pump 2B discharge recirculation valve), on October 10, 2018

(2) Unit 1, WO 40553909, B Train Quarterly Non Check Valve Cycle Test, following replacement of the starter mechanical interlock, on October 23, 2018

(3) Unit 1, WO 40549425, control room air conditioner, HVA/ACC-3B, replace condenser coils, on November 5, 2018

(4) Unit 1, WO 40553904, starter mechanical interlock for shield building flow control valve FCV-25-11, on December 17, 2018

71111.20 - Refueling and Other Outage Activities

Unit 2 Refueling Outage (SL2-24)

The inspectors evaluated Unit 2 refueling outage (SL2-24) activities from August 27, 2018 until the unit was returned to service on October 3, 2018. The inspectors completed inspection procedure 71111.20 with the exception of a partial completion of Section 03.01.e in the prior inspection period as documented in NRC Integrated Inspection report

===05000335/2018003 and 05000389/2018003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18313A180). The remaining portions of Section 03.01.e were completed during this inspection period.

Unit 2 Forced Outage (October 12 - 17, 2018)

On October 12, 2018, the unit experienced an automatic reactor trip from RTP due to a fault on the 2A1 6.9 kV bus during a transfer of the bus power supply from the 2A auxiliary transformer to the 2A SUT. The fault caused a fire in the 2A auxiliary transformer feeder breaker that was extinguished by the onsite fire brigade. The licensee performed minimal work in the reactor containment building that included repair of a leak in the 2A1 reactor coolant pump oil lift pump system. Additionally, repairs were made to the non-safety related 2A1 6.9 kV bus that was damaged by the fire. The unit was maintained at normal operating temperature during the forced outage. The inspectors evaluated Unit 2 forced outage activities from October 12, 2018 until the unit was returned to service on October 17, 2018. The inspectors completed sections 03.01a, 03.01b, 03.01d-1, 2, 4, 11, and 03.01e-1 of inspection procedure 71111.20.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

(1) Unit 2, 2-OSP-08.01, Main Steam Isolation Valve Periodic Test, on October 1, 2018

(2) Unit 2, 2-PTP-81, Reload Startup Physics Testing, on October 2, 2018 In-service test ===

Unit 1, 2-OSP-09.01C, 1C Auxiliary Feedwater Pump Code Run, December 20,

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified the following licensee mitigating system performance indicators submittals listed below for the period of October 1, 2017 through September 30, 2018.

(1) Unit 1, emergency alternating current (AC) power systems

(2) Unit 2, emergency AC power systems

(3) Unit 1, high pressure injection systems

(4) Unit 2, high pressure injection systems

(5) Unit 1, heat removal systems

(6) Unit 2, heat removal systems

(7) Unit 1, residual heat removal systems

(8) Unit 2, residual heat removal systems

(9) Unit 1, cooling water systems

(10) Unit 2, cooling water systems

71152 - Problem Identification and Resolution Semiannual Trend Review

The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue.

71153 - Follow-up of Events and Notices of Enforcement Discretion Personnel Performance

On October 9, 2018 Unit 2 reactor power and reactor coolant system (RCS) temperature began to rise after placing chemical and volume control system 2A ion exchanger in service.

The operators immediately implemented actions to reduce power to RTP. Peak reactor power during the transient was 100.07 percent RTP. The licensee determine that the power change was due to the reactivity addition of adding deborated water to the RCS when the ion exchanger was placed in service. The licensee determined that deborated water leaked past an isolation valve into the ion exchanger while the ion exchanger was in a standby condition. The issue was placed in the licensees corrective action program (CAP) as AR

===2284622. The inspectors determined that the transient was not a result of the operators intentionally operating the unit above the licensed power limit. The 2-hour average and shiftly average power limits were maintained within the regulatory requirements as specified in NRC Regulatory Issue Summary 2007-21, Adherence to Licensed Power Limits, revision 1.

Events ===

(1) On October 12, 2018, the unit 2 experienced an automatic reactor trip from RTP due to a fault on the non-safety 2A1 6.9 kV bus during a transfer of the bus power supply from the 2A auxiliary transformer to the 2A SUT. A non-emergency event report was submitted to the NRC (Event Report 53665). The automatic reactor trip was due to a loss of two reactor coolant pumps that were powered from the bus. The fault caused a fire in the 2A auxiliary transformer feeder breaker that was extinguished by the onsite fire brigade. The 2A1 6.9 kV bus was isolated from the 2A auxiliary feeder breaker, restored, tested and was re-energized using the SUT feeder breaker. The unit was restarted on October 17, 2018 and was returned to RTP on October 18, 2018. The issue was placed in the CAP as AR 2285892 and is associated with the licensee event report (LER) review documented below.

(2) On October 29, 2018, the unit 1 was manually tripped from RTP when steam generator levels could not be maintained when a feedwater transient developed after placing the 5B feedwater heater normal level control valve in service following maintenance. A non-emergency event report was submitted to the NRC (Event Report 53703). After the 5B feedwater heater normal level control valve was placed in service, a transient developed in the 4B feedwater heater level control system that resulted in pressure fluctuations in the feedwater system. The transient resulted in the inability to maintain steam generator level in the 2B steam generator and resultant manual trip of the unit. The 4B feedwater heater level control system was repaired. The unit was restarted on October 30, 2018 and reached RTP on November 1, 2018. The issue was placed in the CAP as AR

===2288575.

Licensee Event Reports ===

The inspectors evaluated the following licensee event report which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) Licensee Event Report (LER) 05000389/2018-002-00, Automatic Reactor Trip Due to a Breaker Failure on the 2A1 6.9 kV Bus

INSPECTION RESULTS

Observations: Trend Review 71152 The inspectors as well as the licensee identified an adverse trend associated with transient combustible controls. The licensee and the inspectors identified transient combustibles in several overhead areas of both units RAB. In most cases, the amount of transient combustible material found was within procedural requirements. The inspectors documented a finding associated with transient combustible control in NRC Integrated Inspection Report 05000335/2018003 and 05000389/2018003 (ML18312A180). The adverse trend and associated corrective actions were documented in the CAP as AR

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

On January 10, 2019, the inspectors presented the quarterly resident inspector inspection results to Mr. Coffey and other members of the licensee staff.

LIST OF

DOCUMENTS REVIEWED

71111.01: Adverse Weather Protection

0-NOP-99.06, Cold Weather Preparations

OP-AA-102-1002, Seasonal Readiness

71111.04: Equipment Alignment

2-NOP-59.01A, 2A Emergency Diesel Generator Standby Alignment

1-NOP-03.11, HPSI System Initial Alignment

2-NOP-14.01, Component Cooling Water System Initial Alignment

2-NOP-02.11, Charging And Letdown Initial Alignment

71111.05: Fire Protection

ADM-0005729, Fire Protection Training, Qualification and Requalification

ADM-19.02, Pre-Fire Plan Standard Operating Procedure

71111.11: Licensed Operator Requalification Program and Licensed Operator

Performance

2-EOP-01, Standard Post Trip Actions SPTA

2-EOP-02, Reactor Trip Recovery

2-EOP-04, Steam Generator Tube Rupture SGTR

2-AOP-08.02 Steam Generator Tube Leak

2-AOP-22.01, Rapid Downpower

2-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1

71111.12: Maintenance Effectiveness

ER-AA-100-2002, Maintenance Rule Program Administration

SCEG-004, Guideline for Maintenance Rule Scoping, Risk Significant Determination, and

Expert Panel Activities

71111.13: Maintenance Risk Assessments and Emergent Work Control

OP-AA-104-1007, Online Aggregate Risk

WCG-016, Online Work Management

71111.18: Plant Modifications

EN-AA-205-1100, Design Change Packages

71111.20: Refueling and Other Outage Activities

ADM-09.23, Outage Risk Assessment and Control

1-GMM-68.02, Emergency Closure of Containment Penetrations, Personnel Hatch, and

Equipment Hatches

1-NOP-03.05, Shutdown Cooling

1-NOP-01.05, Filling and Venting RCS

1-NOP-02.02, Charging and Letdown

ADM-09.26, Shutdown Cooling Controls

1-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2

1-GOP-303, Reactor Plant Heatup - Mode 3 < 1750 to Mode 3 > 1750

1-GOP-365, Refueling Sequence Guidelines

1-GOP-403, Reactor Plant Heatup - Mode 4 to Mode 3

1-GOP-504, Reactor Plant Startup - Mode 5 to Mode 4

71111.22: Surveillance Testing

ADM-29.02, ASME Code Testing of Pumps and Valves

71151: PI Verification Inspection

Procedures, Guidance Documents and Manuals

LI-AA-100-10003, NRC Performance Indicator

71153: Follow-up of Events and Notices of Enforcement Discretion

Drawing 2998-G-078, Flow Diagram Chemical and Volume Control System, Sheet 120

Drawing 2998-G-084, Flow Diagram Domestic & Make-up Water Systems, Sheet 1

Operations Adverse Condition Monitor Plan, dated October 9, 2018 for enhanced control during

any dilution or boration

2-EOP-01, Standard Post Trip Actions SPTA, revision 38

2-EOP-02, Reactor Trip Recovery, revision 26

Pre-fire plan PFP-2-TB-19.5, Unit 2 Turbine, revision 1

2-AOP-100.01, Response to Fire, revision 8

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