IR 05000335/2018001
| ML18121A344 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/01/2018 |
| From: | Randy Musser NRC/RGN-II/DRP/RPB3 |
| To: | Nazar M Florida Power & Light Co |
| References | |
| IR 2018001 | |
| Download: ML18121A344 (25) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION May 1, 2018
SUBJECT:
ST. LUCIE PLANT - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000335/2018001 AND 05000389/2018001
Dear Mr. Nazar:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your St. Lucie Plant Units 1 and 2. On April 19, 2018, 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.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
The finding did not involve a violation of NRC requirements.
If you disagree with the finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC resident inspector at the St. Lucie Plant. 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 Ryan C. Taylor Acting for/
Randall A. Musser, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos.: 50-335, 50-389 License Nos.: DPR-67, NPF-16
Enclosure:
IR 05000335/2018001 and 05000389/2018001
REGION II==
Docket Nos: 50-335, 50-389 License Nos: DPR-67, NPF-16 Report Nos: 05000335/2018001, 05000389/2018001 Enterprise Identifier: I-2018-001-0062 Licensee: Florida Power & Light Company (FPL)
Facility: St. Lucie Plant, Units 1 and 2 Location: 6501 South Ocean Drive Jensen Beach, FL 34957 Dates: January 1, 2018 through March 31, 2018 Inspectors: T. Morrissey, Senior Resident Inspector S. Roberts, Resident Inspector W. Pursley, Health Physicist (Sections 71124.01, 71124.07 and 71151)
J. Panfel, Health Physicist (Sections 71124.06 and 71151)
J. Rivera, Health Physicist (Section 71124.08)
A. Butcavage, Reactor Inspector (Section 71111.08)
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. NRC and self-revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations Improper Evaluation of LCV-9005 position setpoints Leads to AFAS Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Green Finding None 71153 Systems FIN 05000389/2018001-01 Closed A self-revealed Green finding was identified when the licensee failed to properly evaluate a discrepancy between A and B feedwater bypass level control valve positions, as required by licensee procedures PI-AA-205, Condition Evaluation and Corrective Action, and PI-AA-100-1008, Condition Evaluation.
Additional Tracking Items Type Tracking number Title Report Section Status Licensee 05000389/2017-004-00 Automatic Reactor 71153 Closed Event Trip due to Report Turbine Control (LER) System Malfunction
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On March 11, 2018, the control room operators commenced a planned power reduction and manually tripped the reactor from 25 percent RTP on March 12, 2018 to start a planned refueling outage. Unit 1 was shutdown in Mode 6 at the conclusion of the inspection period.
Unit 2 operated at or near 100 percent 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 Impending Severe Weather
The inspectors evaluated readiness for impending adverse cold weather conditions below 40 degrees Fahrenheit on January 4-5, 2018.
71111.04 - Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, 1B high pressure safety injection (HPSI) train with 1A HPSI train out of service (OOS) for planned maintenance on January 9, 2018
- (2) Unit 2, 2A and 2B auxiliary feed water (AFW) trains while the 2C AFW train was OOS for planned and emergent maintenance on January 17, 2018
- (3) Unit 2, 2A emergency diesel generator (EDG) while 2B EDG was OOS for an extended planned outage on January 23-25, 2018
71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 2, cable spreading room on January 14, 2018
- (2) Unit 2, spent fuel handing building on February 7, 2018
- (3) Unit 1, 1B EDG room on February 23, 2018
- (4) Unit 1, reactor containment building (RCB) 62 foot (ft.) elevation on March 21, 2018
- (5) Unit 1, RCB 18 ft. and 23 ft. elevations on March 21, 2018
Annual Inspection (1 Sample)
The inspectors evaluated fire brigade performance during two separate drills on January 12, 2018 and February 5, 2018. In addition, the inspectors evaluated fire brigade performance on March 23, 2018, when responding to a Unit 1 fire resulting from a degraded welding cable that was extinguished prior to arrival of the fire brigade. The inspectors also evaluated the licensees self-contained breathing apparatus (SCBA) program including storage, training, expectations for use, and maintenance.
71111.06 - Flood Protection Measures Internal Flooding
The inspectors evaluated internal flooding mitigation protections in the Unit 2 reactor auxiliary building (RAB) -0.5 ft. elevation on February 27, 2018.
71111.07A - Heat Sink Performance
On March 14, 2018 the inspectors evaluated the readiness and availability of Unit 1, 1A component cooling water (CCW) heat exchanger (HX) by verifying periodic maintenance methods outlined in Electric Power Research Institute (EPRI) HX performance monitoring guideline, NP-7552, were utilized.
71111.08 - Inservice Inspection Activities
The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from March 19 - 23, 2018:
- (1) Magnetic Particle (MT)a) Work Order 40497052-02, Weld Traveler No. 02029-018683, Weld Number 02029, ASME Code Class 3. Pipe to Pipe, Intake Cooling Water pressure boundary weld.
(reviewed)b) Work Order 40497052-02, Weld Traveler No. 02030-18646, Weld Number 02030, ASME Code Class 3, Pipe to Pipe, Intake Cooling Water pressure boundary weld.
(reviewed)c) Report No. PSL-1-MT-18-002, Summary No. SL1-010920, Component Id: RV Support @180 Degrees (B Hot Leg), ASME Code Class 1. (reviewed)
- (2) Ultrasonic (UT)a) Summary No. 001500, Reactor Vessel Upper Shell to Intermediate Shell, Component Id: 8-203, Weld W02, Flaw No. 2, ASME Class 1, March 22, 2018 (observed Level III review of UT data)b) Flaw Evaluation Summary Sheet, Weld W02, Flaw No. 2, ASME Class 1, November 4, 2008 (Observed/Discussed Level III review comparison to previous 2008 UT data)c) Summary No. 002300, Reactor Vessel Inlet Nozzle at 120 Degrees, Nozzle to Shell Weld from Vessel Inside Diameter, Component Id: 4-205-A, Weld W27, Flaw No. 2, ASME Class 1, March 22, 2018 (observed Level III review of UT Data)d) Flaw Evaluation Summary Sheet, Weld W27, Flaw No. 2, ASME Class 1, November 4, 2008 (Observed/Discussed Level III review/comparison to previous 2008 UT data)
- (3) Visual (VT-3)a) VT Data Sheet No. 4.15-001, Reactor Pressure Vessel Upper Head, Bare Metal Visual Examination, In-Core Instrumentation Penetration No. 3, March 27, 2018 (reviewed)b) Report No. PSL-1-VT-18-001, Summary No. SL1-010910, Component Id: RV Support @180 Degrees (B Hot Leg), ASME Code Class 1. (reviewed)
The Inspectors evaluated the licensees boric acid control program performance and performed walk-down inspections of the reactor containment building.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification - 71111.11Q
On January 29, 2018, the inspectors observed and evaluated a licensed operator crew during an evaluated emergency plan evaluation on the control room simulator. The simulated scenario included an excessive steam demand, a manual reactor trip, and failure of engineered safety features activation system (ESFAS) which caused the control team to manually initiate emergency boration. A fire alarm in containment resulted in an Unusual Event emergency classification which required a simulated notification to the State of Florida and the NRC.
Operator Performance - 71111.11Q (1 Sample)
The inspectors observed and evaluated operator performance during a shut down and cool down of Unit 1 to support a planned refueling outage on March 11-12, 2018.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (2) Unit 2, AR 2232840, A train main feed isolation valve (MFIV) failure
Maintenance Rule (a)(3) periodic assessment (1 Sample)
The inspectors reviewed the licensees Maintenance Rule periodic assessment as documented in AR 2238173 on January 25, 2018
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 risk with 2C AFW pump OOS to replace an electrical relay and 2A CCW HX OOS for planned cleaning on January 17-18, 2018
OOS for planned maintenance on February 5, 2018
- (5) Unit 1, yellow risk shutdown safety assessment with the reactor coolant system (RCS) at lowered inventory to support reactor vessel head removal on March 14-16, 2018
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (2) Unit 2, AR 2245486, control room envelope negative differential pressure while in recirculation mode on February 8, 2018
- (3) Unit 1, AR 2249125, control room outside air intake radiation monitors (RIS-26-84, -85)did not cause a Fail Alarm during testing on February 21, 2018
- (4) Unit 1, AR 2252656, shield building ventilation high efficiency particulate air filter test results just below specification on March 7, 2018
- (5) Unit 1, ARs 2253859, 2253860, 1A EDG did not meet surveillance acceptance criteria on March 13, 2018
- (6) Unit 1, AR 2255986, refueling water tank linear stress cracks on March 26, 2018
71111.18 - Plant Modifications
The inspectors evaluated the following temporary or permanent modifications:
Engineering change (EC) 290453, auxiliary feedwater actuation system (AFAS) relay modification February 13, 2018
71111.19 - Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) Unit 2, 2-OSP-69.24, Engineered Safeguards Relay Test, Train A, after replacing a failed relay for HPSI valve HCV-3627 in accordance with work order (WO) 40580192 on January 3, 2018
- (2) Unit 2, WOs 40521474 and 40521492, post-maintenance test instructions after performing 2C AFW pump trip and throttle valve lubrication and spring testing in accordance with the same WOs on January 8, 2018
- (3) Unit 2, 2-OSP-99.08A, A Train Quarterly Non Check Valve Cycle Test, after replacing the 2A CCW HX temperature control valve per WO 40571871 on January 19, 2018
- (4) Unit 2, 2-SMI-09.40, Auxiliary Feedwater Actuation System Actuation Relay Test, after rewiring a relay per WO 40582284 on January 17, 2018
- (5) Unit 1, 1-OSP-99.08B, B Train Quarterly Non Check Valve Cycle Test, after performing preventative maintenance on 1B LPSI suction valve V3432 per WO 40474746, on January 26, 2018
==71111.20 - Refueling and Other Outage Activities (Partial Sample)
The inspectors evaluated Unit 1 refueling outage (SL1-28) activities from March 12, 2018 to March 31, 2018. The inspectors completed inspection procedure Sections 03.01.a, 03.01.b, and 03.01.c. The inspectors partially completed the remaining inspection procedure sections. These inspection procedure sections will be completed during the second quarter of 2018.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine==
- (1) Unit 2, 2-OSP-59.01A, 2A Emergency Diesel Generator Monthly Surveillance, (fast start) on January 8, 2018
- (2) Unit 2, 2-SME-09.40, Auxiliary Feedwater Actuation System Actuation Relay Test, on January 16, 2018
- (3) Unit 1, 1-OSP-69.13A, ESF Staggered 36 Month Surveillance For SIAS/CIS/CSAS -
Train A, on March 13, 2018 In-service (2 Samples)
- (1) Unit 2, 2-OSP-03.06B, 2B Low Pressure Safety Injection Pump Code Run, on February 20, 2018
- (2) Unit 1, 1-OSP-03.06A, 1A Low Pressure Safety Injection Pump Code Run, on
March 7, 2018 Containment Isolation Valve (1 Sample)
Unit 1, 1-OSP-68.02, Local Leak Rate Test (penetration 56) on March 19, 2018
71114.06 - Drill Evaluation Emergency Planning Drill
On January 10, 2018, the inspectors evaluated an emergency response drill that included a major loss of control room annunciators, a steam generator tube leak, loss of condenser vacuum, a manual reactor trip, a steam generator tube rupture, and a stuck open main steam safety valve.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment
===The inspectors evaluated radiological hazards assessments and controls.
Instructions to Workers===
The inspectors evaluated worker instructions.
Contamination and Radioactive Material Control (1 Sample)
The inspectors evaluated contamination and radioactive material controls.
Radiological Hazards Control and Work Coverage (1 Sample)
The inspectors evaluated radiological hazards control and work coverage.
High Radiation Area and Very High Radiation Area Controls (1 Sample)
The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walkdowns and Observations
The inspectors evaluated the licensees radioactive gaseous and liquid effluent treatment systems during plant walkdowns.
Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)
The inspectors evaluated the licensees gaseous and liquid effluent monitor instrument calibration and testing.
Sampling and Analyses (1 Sample)
The inspectors evaluated radioactive effluent sampling and analysis activities.
Instrumentation and Equipment (1 Sample)
The inspectors evaluated radioactive effluent instrumentation and equipment.
Dose Calculations (1 Sample)
The inspectors evaluated dose calculations.
71124.07 - Radiological Environmental Monitoring Program Site Inspection
The inspectors evaluated the licensees radiological environmental monitoring program.
Groundwater Protection Initiative Implementation (1 Sample)
The inspectors evaluated the licensees groundwater monitoring program.
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation Radioactive Material Storage
The inspectors evaluated the licensees radioactive material storage.
Radioactive Waste System Walkdown (1 Sample)
The inspectors evaluated the licensees radioactive waste processing facility during plant walkdowns.
Waste Characterization and Classification (1 Sample)
The inspectors evaluated the licensees radioactive waste characterization and classification.
Shipment Preparations (1 Sample)
The inspectors evaluated the licensees radioactive material shipment preparation processes.
Shipment Records (1 Sample)
The inspectors evaluated the licensees non-excepted package shipment records.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified the following licensee performance indicators submittals for the periods listed below.
- (1) Radiological Effluent TS/ODCM Radiological Effluent Occurrences from April 1, 2017, through December 31, 2017
- (2) Occupational Exposure Control Effectiveness from April 1, 2017, through December 31, 2017
- (3) Unit 1, Unplanned Scrams per 7000 Critical Hours from January 1, 2017, through December 31, 2017
- (4) Unit 2, Unplanned Scrams per 7000 Critical Hours from January 1, 2017, through December 31, 2017
- (5) Unit 1, Unplanned Power Changes per 7000 Critical Hours from January 1, 2017, through December 31, 2017
- (6) Unit 2, Unplanned Power Changes per 7000 Critical Hours from January 1, 2017, through December 31, 2017
- (7) Unit 1, Unplanned Scrams With Complications from January 1, 2017, through December 31, 2017
- (8) Unit 2, Unplanned Scrams With Complications from January 1, 2017, through December 31, 2017
71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues
The inspectors reviewed the licensees implementation of its corrective action program related to the following issue. The issue was selected due to its repetitive nature.
2B CCW HX (ARs 2216036 and 2225449), which detailed actions taken to address tube leakage most likely caused by a combination of erosion and corrosion as a result of a stuck shell on the inside of a tube.
71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports
The inspectors evaluated the following Licensee Event Report (LER) which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
LER 05000389/2017-004-00, Automatic Reactor Trip due to Turbine Control System Malfunction, on October 26,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation
During the week of January 29, 2018, the inspectors, through direct observation and independent evaluation, observed the loading of dry shielded cask (DSC)-084 from the Unit 2 spent fuel pool. The inspectors verified the cask loading activities were performed in a safe manner and in compliance with approved procedures. Based on direct observation and review of selected records, the inspectors verified the licensee had properly identified each fuel assembly placed in DSC-084. Additionally, through direct observation, the inspectors verified the licensee had properly placed DSC-085 in the Independent Spent Fuel Storage Installation (ISFSI). The inspectors also observed activities associated with the transport and storage of casks, loading of spent fuel in casks, vacuum drying and seal welding activities, and the heavy lifts to remove the casks from the spent fuel pool and placing them in the cask handling facility.
INSPECTION RESULTS
Improper Evaluation of LCV-9005 Position Setpoints Leads to AFAS Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Green Finding None 71153 Systems FIN 05000389/2018001-01 Closed A self-revealed Green finding was identified when the licensee failed to properly evaluate a discrepancy between A and B feedwater bypass level control valve positions, as required by licensee procedures PI-AA-205, Condition Evaluation and Corrective Action, and PI-AA-100-1008, Condition Evaluation.
Description:
On November 19, 2013, during reactor startup activities, feedwater bypass valves, A (LCV-9005) and B (LCV-9006), were found to be operating at different throttle positions while maintaining their respective steam generator water levels. Valves LCV-9005 and 9006 were both originally installed in April 1978. LCV-9005 was replaced in 1994, with an equivalent valve, due to obsolescence. The original valve had a full open stroke length of 1.5 inches (in.), while the new equivalent valve had a full open stroke length of 2 in. to provide the same flow as the original valve. When installed, LCV-9005 was set up to limit its stroke length to 1.5 in., matching the replaced valve, and the associated drawings were never revised to show that the new valve had a full 2 in. open stroke length. In 2009, the distributed control system (DCS) was installed utilizing these drawings and was setup under the assumption that both valves, LCV-9005 and LCV-9006, were the same model valves and stroke lengths.
The DCS system was designed to provide a signal to throttle the feedwater bypass valves following a reactor trip to 20 percent open to provide approximately 5 percent feed flow in order to recover steam generator water levels utilizing main feedwater. During Unit 2 startup activities in November 2013, the licensee noted a discrepancy in the valve positions for LCV-9006 and LCV-9005 when they were providing steam generator water level control.
The licensee placed the issue in the corrective action program under Action Request (AR)1921720 and determined that it was necessary to evaluate a revision of the LCV-9005 DCS setpoint, which was accomplished by an engineering condition evaluation under AR 1925428. The engineering condition evaluation was inadequate in that it failed to recognize the differences in the two different model valves, and therefore failed to provide adequate corrective actions to address performance issues associated with these differences.
The final recommendation from AR 1925428 was that the current LCV-9005 setting did not impose any risk to the plant operation, as the 2A steam generator level had been within acceptable range with no control room alarm observed. Therefore, no setpoint change was required at that point.
On October 26, 2017, following a Unit 2 trip, LCV-9005 was sent a digital DCS demand signal to be 20 percent open. Since the valve was locally set to have a maximum stroke of 1.5 in. instead of 2 in. open, the actual flow through the valve was less than 5 percent. This resulted in flow lower than needed to maintain 2A steam generator level, and caused level to lower, which eventually resulted in an actuation of the A train auxiliary feedwater actuation system (AFAS).
Corrective Action(s): The licensee implemented corrective actions to: 1) properly set up LCV-9005 in order for it to have a full stroke length of 2 inches so that it could provide the required feedwater flow and, 2) update associated drawings to include correct stroke lengths.
Corrective Action Reference(s): This issue was entered into the licensees CAP as AR 2232869
Performance Assessment:
Performance Deficiency: The failure to properly evaluate a discrepancy between the A and B feedwater bypass level control valve positions, as required by licensee procedures PI-AA-205, Condition Evaluation and Corrective Action, and PI-AA-100-1008 Condition Evaluation, was a performance deficiency.
Screening: The inspectors determined that the performance deficiency was more than minor because it was associated with the Mitigating Systems cornerstone attribute of human performance and adversely affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). Specifically, the licensee conducted an ineffective condition evaluation of a noticeable difference between the A and B feedwater bypass level control valve positions, discovered during a Unit 2 reactor startup on November 19, 2013. This failure of their CAP, to ensure this issue was adequately resolved, resulted in inadequate feed flow to the 2A steam generator, following a Unit 2 trip in 2017, which resulted in a lowered steam generator level and caused an actuation of the A train AFAS.
Significance: Using Inspection Manual Chapter (IMC) 0609, Attachment 4, Initial Characterization of Findings, Table 2, the finding was determined to affect the Mitigating Systems cornerstone due to degradation to main feedwater which affected decay heat removal. IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, was used to further evaluate this finding. The finding screened as Green because the deficiency did not affect the design or qualification of a mitigating structure, system, and component (SSC)and the SSC maintained its operability or functionality. This finding did not present an immediate safety concern and there were no compensatory measures in place while the licensees long-term corrective actions were being implemented.
Cross-cutting Aspect: No cross cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
The inspectors did not identify a violation of regulatory requirements associated with this finding.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On January 26, 2018, the inspectors presented the radiation protection inspection results to Mr. DeBoer, Site Director, and other members of the licensee staff.
On March 23, 2018, the inspectors presented the inservice inspection and radiation protection results to Mr. DeBoer, Site Director, and other members of the licensee staff.
On April 19, 2018, the inspector presented the quarterly resident inspector inspection results to Mr. DeBoer and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01: Adverse Weather Protection
0-NOP-99.06, Cold Weather Preparations
71111.04: Equipment Alignment
1-NOP-03.11, High Pressure Safety Injection Initial Alignment
2-NOP-09.11, Auxiliary Feedwater System Initial Alignment
2-NOP-59.01A, 2A Emergency Diesel Generator Standby Alignment
71111.05: Fire Protection
ADM-0005729, Fire Protection Training, Qualification and Requalification
ADM-19.02, Pre-Fire Plan Standard Operating Procedure
71111.06: Flood Protection Measures
2-AOP-24.01, RAB Flooding
WO 40497180, ESFAS Sump LS-06-1B Calibration
WO 40502838, ESFAS Sump LS-06-1A Calibration
71111.08 Inservice Inspection Activities
Procedures:
ADM-17.29, Reactor Vessel Internals Aging Management Program, Rev. 6
CY-SL-108-0002, High Activity in a Steam Generator, Rev. 2
ER-AP-116-1000, Nuclear Fleet Administrative Procedure, Boric Acid Corrosion Control
Program, Rev. 2
NDE-4.15, Manual Examination Procedure, Component, Support & Inspection, Visual
Examination (VE), ASME Section XI, Code Case N-722-1 and N-729-4, 3/12/18
54-ISI-364-008, NDE Procedure, Remote Underwater Visual Examination of Reactor Pressure
Vessels, Vessel Internals, and Components in Pressurized Water Reactors in Accordance
with Section XI. 2/8/18
54-ISI-801-003, Nondestructive Examination Procedure, Automated UT of PWR Vessel Shell
Welds, 9/4/15
Drawings:
8770-G-068, Florida Power and Light St Lucie Plant, General Arrangement, Reactor Building
Sections, Sheet 2, Rev. 19
8770-G-365, Florida Power and Light Hutchinson Island Plant, El. 18, Reactor Containment
Building Sections El. 18 0 , Sheet 2, Rev. 57
E-233-496, Ebasco Services, General Arrangement Elevation, Reactor Vessel, Rev. 6
E-233-496, Ebasco Services, As-Built Reactor Vessel, Rev 4
CB Elev. OD (PSL-1), Outside Diameter, Plant St. Lucie, Unit-1, Core Barrel Elevation Plant
Saint Lucie-1 (Sketch), Rev. 1
CB Elev. (PSL-1) Shroud Plate Numbering (Sketch), Rev. 3
RPV-CB Plan (PSL-1), Core Barrel in Reactor Vessel (Sketch), Rev. 2
UGFAP (PSL-1), Upper Internals Assembly Fuel Alignment Plate Bottom View (Sketch), Rev. 1
UGS (PSL-1), Upper Guide Structure (Sketch), Rev.1
01-001-G, Florida Power and Light, St. Lucie Unit-1, Reactor Pressure Vessel Upper and Lower
Internal Assembly (Sketch), Rev. 2
Self-Assessments:
2079327, Quick Hit, Department Assessment Report, St Lucie Units 1 & 2, Boric Corrosion
Control Program (BACCP), 6/28/16
Work Orders/Work Requests:
289976-01, SL1-28, Att. 1, Thimble Inspection, 3/30/18
40497052, SL1, Intake Cooling Water (CW-78) West Shear Wall Penetration Replacement,
3/23/28
40513412, SL1, Rx Vessel-Reactor Vessel Internals Program (MRP-227) Inspections SL1-28,
2/1/18
40516114, SL1, ISI Reactor Vessel, 3/14/18
289976, SL1, Inspect ICI Thimble Zircaloy Section AR 1845589, 3/20/18
Action Requests:
AR-01845589, Engineering Review of Westinghouse Letter FPL-13-5, Operating Experience for
In-Core Instrumentation Thimble Failure at a similar facility, 2/5/13
AR-02254768, Thimble in ICI location W-4, Through Wall Wear, 3/19/18
AR-02253932, Pipe Support Snubber 121 Found Disconnected from End Attachment, 3/13/18
AR-02199850, Wet Brown Boric Acid Apparent on 1B Charging Pump Plunger, 4/19/17
AR-02186650, Valve 03993, Active Boric Acid Leak at Packing, 2/20/17
AR-02209017, Valve 5203, Active Boric Acid Leak on Downstream Side, 6/7/2017
AR-02255865, Linear Indications on Core Support Barrel-MRP-227 Exams, 3/23/18
Miscellaneous Documents:
AIM 160810113-2Q-3, Condition Monitoring and Operational Assessment for the St. Lucie Unit
Steam Generators Based on Eddy Current Examination End of Cycle 26, October 2016,
January, 2017
EC 280215, Snubber Acceptance Testing Criteria, Rev.19
FP&L, Under Vessel Photograph No. 8, Reactor Support Column, 3/22/18
FP&L, Under Vessel Photograph No. 11, Reactor Support Column, 3/22/18
FP&L, Under Vessel Photograph No. 15, Reactor Support Column, 3/22/18
Framatome Visual Inspection Summary List, Prior to performing Exams, 3/16/18
Intertek Letter, Review of Operation and degradation assessments for St. Lucie Unit-1 Steam
Generators for Cycle 27, 11/6/17
LTR-AMLR-18-22 Disposition of Indications Observed in the Core Support Barrel at SL1,
(Westinghouse, Ref: 18-36) 3/30/18
MRP-228, Electric Power Research Institute, Materials reliability Program, Inspection Standard
for Pressurized Water Reactor Internals, 2015 Update, Rev. 2
NDE Personnel Qualification and Certification Records for
- M. Hacker, D. Langenfeld
PSL-ENG-LRAM-15-002, Reactor Vessel Internals Inspection Program-License Renewal Basis
Document, Rev.4
Report Number 1101242.410, Piping Stress Analysis Report for the Auxiliary Spray Piping
Calculation 3900001-004, St Lucie Nuclear Power Plant Unit-1, 11/4/11
St Lucie Unit-1, Fourth In-Service Inspection Program Plan, Revision 5, 3/5/18
St Lucie Unit-1, Fifth In-Service Inspection Program Plan, Revision 0, 2/10/18
54-ISI-364-008, NDE Procedure, Remote Underwater Visual Examination of Reactor Pressure
Vessels, Vessel Internals, and Components in Pressurized Water Reactors in Accordance
with Section XI. 2/8/18
54-ISI-801-003, Nondestructive Examination Procedure, Automated UT of PWR Vessel Shell
Welds, 9/4/15
71111.11: Licensed Operator Requalification Program and Licensed Operator
Performance
2-AOP-01.10, Pressurizer Pressure and Level
2-AOP-01.08, Reactor Coolant System Leakage
2-AOP-08.01, Steam Leak
2-AOP-22.01, Rapid Down Power
2-AOP-100.01, Response to Fire
2-EOP-01, Standard Post Trip Actions
2-EOP-05, Excess Steam Demand Event
EPIP-01, Classification of Emergencies
EPIP-02, Duties and Responsibilities of the Emergency Coordinator
EPIP-08, Offsite Notifications and Protective Action Recommendations
1-GOP-123, Turbine Shutdown - Full Load To Zero Load
1-EOP-01, Standard Post Trip Actions
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
OM-AA-101-1000, Shutdown Risk 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-01.03, Draining RCS
1-NOP-01.05, Filling and Venting RCS
1-NOP-02.02, Charging and Letdown
ADM-09.26, Shutdown Cooling Controls
1-GOP-305, Reactor Plant Cooldown - Hot Standby To Cold Shutdown
1-GOP-365, Refueling Sequence Guidelines
1-NOP-67.02,Spent Fuel Handling Machine Operation
1-NOP-67.04, Refueling Machine Operation
0-NOP-67.05, Refueling Operation
71111.22: Surveillance Testing
ADM-29.02, ASME Code Testing of Pumps and Valves
71124.01: Radiological Hazard Assessment and Exposure Controls
Procedures, Guidance Documents, and Manuals
ADM-05.06, Control of Radioactive Material, Revision (Rev.) 3
HPP-1, Preparing Radiation Work Permits, St. Lucie Plant, Rev. 40
HPP-41, Movement of Material and Equipment, Rev. 38
RP-AA-100, Radiation Protection Administrative Program, Rev. 07
RP-AA-102-1001, Area Radiological Surveys, Rev. 04
RP-AA-103-1001, Posting Requirements for Radiological Hazards, Rev. 04
RP-AA-103-1002, High Radiation Area Controls, Rev. 08
RP-AA-103-1006, Conduct Of Radiological Diving Operations, Rev. 5
RP-AA-107-1002, Requirements for Radioactive Materials Stored Outdoors, Rev. 07
RP-AA-107-1003, Unconditional and Conditional Release of Material, Rev. 04
RP-AA-107-1004, Procedure for Radioactive Source Controls and Leak Checking, Rev. 0
RP-SL-101-1003, Personnel Contamination Monitoring and Decontamination, Rev. 02
Records and Data
RP-AA-107-1004-F02: Source Leak Test and Inventory Form, 1/12/2018
RP-AA-107-1004-F02: Source Leak Test and Inventory Form, 2/12/2018
RP-SL-103-2005, U1 and U2 Spent Fuel Pool Non-SNM Item Inventory Log Sheet, 11/14/17
Air Sample Data Summary Sheet #181-0098, U1 RCB 62 During Filling of Rx Cavity,
03/16/2018
Air Sample Data Summary Sheet #181-0231, U1 RCB Keyway/Under Vessel, 03/22/2018
Air Sample Data Summary Sheet #181-0208, U1 RCB 62 During Core Barrel Move, 03/21/2018
Air Sample Data Summary Sheet #181-0223, U1 RCB Top of Pressurizer During Removal of
Code Safeties, 03/21/2018
Air Sample Data Summary Sheet #181-0151, U1 SFP 62 During Fuel Movement, 03/18/2018
Radiological Work Permit (RWP) 18-1039, Core Support Barrel, Lift Rigs: Remove/Replace. All
Support Work, Rev. 06
RWP-18-1352, Keyway and Beneath the Reactor Vessel Activities, Rev. 01
RWP-18-1410, Pressurizer Code Safetys, Rev. 0
RWP-18-1317, Lower Cavity Survey / Decon Activities, Rev. 0
RWP 18-1112, Remove, Install, Transfer Excore Detector #10 Under Vessel, Rev. 0
Survey PSL-M-20180322-16, HPS-63 U1 RCB Under Rx Vessel Survey/Inspection, 03/22/2018
Survey PSL-M-20161019-26, HPS-63 U1 RCB Under Rx Vessel Survey/Inspection, 10/19/2016
Survey PSL-M-20180318-16, HPS-63 U1 RCB 62 Fuel Movement Dose Rates, 03/18/2018
Survey PSL-M-20180322-7, HPS-11; Core Barrel Lift Rig Verification, 03/22/2018
Survey PSL-M-20180320-33, HPS-11; 62 RCB Down Posting During Core Barrel, 03/20/2018
Survey PSL-M-20180322-5, HPS-64; Code Safetys, 03/22/2018
STL Radiation Protection Plan - SL1-28, 10 Y ISI RX Vessel/Core Support Barrel Lift,
03/19/2018
Corrective Action Program (CAP) Documents
AR 02187400
AR 02191149
AR 02203094
AR 02220303
AR 02254603
71124.06: Radioactive Gaseous and Liquid Effluent Treatment
Procedures and Guidance Documents
1-IMP-26.12, Liquid Radwaste Discharge Process Monitor Functional and Calibration
Instructions, Rev. 13
1-SMI-26.72, Calibration of Plant Vent Stack Radiation Monitor, Rev. 1
2-IMP-26.03, Secondary Calibration of Wide Range Gas Monitors (WRGM), Rev. 13
2-IMP-26.06, Secondary Calibration of Particulate Iodine and Gas (PIG) Monitors, Rev. 13
C-200, Offsite Dose Calculation Manual (ODCM), Rev. 50
CY-SL-102-0025, Determination of Gases, Rev. 3
CY-SL-102-0104, Processing Aerated Liquid Wastes, Rev. 9
CY-SL-102-0105, Processing Gaseous Waste, Rev. 6
CY-SL-104-0112, Determination of Process Radiation Monitor Setpoints, Rev. 9
CY-SL-104-1011, Unit 1 Gaseous Effluent Grab Sampling, Rev. 8
CY-SL-104-2011, Unit 2 Gaseous Effluent Grab Sampling, Rev. 6
CY-SL-108-0003, Alternate Methods for Effluent and Process Radiation Monitors, Rev. 4
EPIP-01, Classification of Emergencies, Rev. 26
Records and Data Reviewed
2015 and 2016 Annual Radioactive Effluent Release Reports
Analytics Inc. Cross Check, 12/22/2016
Gas Release Permit No. G-17-474-B, 1A Gas Decay Tank, 12/13/17
Gas Release Permit No. G-17-473-B, Unit 1 Mini-Purge, 12/13/2017
Liquid Release Permit Nos. L-17-068-B and L-17-069-B, Waste Monitor Tank A
PSL Rx1 EAL DBD, PSL NEI-99-01 EALs, Basis for Radiation Monitor Values Used to Classify
Emergencies, Rev. 3
PSL-ENG-SENS-00-108, Safety Evaluation 2000 FSAR Review, Rev. 1
PSL-ENG-SENS-05-033, Analysis of Acceptability of Anisokinetic Sampling of Main Plant Vent,
FHB Vent, and ECCS Vent Exhaust, Rev. 2
PSL-ENG-SENS-16-002, Unit 1 Ventilation Effluent Radiation Monitors Representative
Sampling, Rev. 0
Unit 1 and Unit 2 System Health Reports, Radiation Monitoring, 2017
Visual Inspection, Leak Test, and Velocity Traverse, Unit 1 Main Stack, 1 HVE-10 (A+B) and 1
HVE-9 (A+B), 09/8/16
Visual Inspection, Leak Test, and Velocity Traverse, Unit 2 Main Stack, 2 HVE-10 (A+B), 2
HVE-9 (A+B) and 2 HVE-16, 2/6/17
WO 40340570-01, RE-6627 Liquid Rad Waste Monitor Calibration, 01/15/16
WO 40471192-01, RE-6627 Liquid Rad Waste Monitor Calibration, 07/06/17
WO 40348630-01, U1 RM-26-13 Plant Vent Stack PIG Calibration, 01/07/16
WO 40478509-01, U1 RM-26-13 Plant Vent Stack PIG Calibration, 08/09/17
WO 40283944-01, RSC-26-1 Stack Exhaust WRGM Channel Calibration, 02/20/15
WO 40405767-01, RSC-26-1 Stack Exhaust WRGM Channel Calibration, 09/07/16
WO 40346919-01, RIM-26-90 Plant Vent Gas WRGM Calibration, 03/02/16
WO 40485932-01, RIM-26-90 Plant Vent Gas WRGM Calibration, 09/01/17
WO 40411588-01, U1 RSC-26-4 Fuel Handling Building PIG Calibration, 11/29/16
CAP Documents
Action Request (AR) 02103930
AR 02121876
AR 02167133
AR 02180001
AR 02205687
AR 02224363
AR 02226671
71124.07: Radiological Environmental Monitoring Program (REMP)
Procedures and Guidance Documents
Sampling Procedure 1, Collection of Air Particulates and Radioiodines, Rev. No. 11
Sampling Procedure 4, Collection of Surface Water, Rev. No. 7
Sampling Procedure 5, Collection of Broadleaf Vegetation, Rev. No. 4
Sampling Procedure 12, Annual Land Use Census, Rev. No. 2
Technical Manual 2, Lower Limits of Detection, Rev. 5
C-200, St. Lucie Plant Chemistry Offsite Dose Calculation Manual, Rev. 50
CY-SL-100-0002, Chemistry Department Groundwater Protection Program, Rev. 5
LI-AA-102-1001, Regulatory Reporting, Rev. 20
Records and Data Reviewed
2015 and 2016 Annual Radiological Environmental Operating Reports St. Lucie Plant Units 1 &
2016 Annual Radioactive Effluent Release Report St Lucie Plant Units & 2
2018 St. Lucie Dry Active Waste 10CFR61 Analysis, 01/16/2018
CFR 50.75(g) documentation, Leak of V06231, Dated 10/27/17
CFR 50.75(g) documentation, Leak of U2 RWST FLEX Connection (AR02203932),
05/08/2017
Air Sampler Flow Calibrations for Location H14, Serial #8191844, 12/01/2017, Location H30,
Serial #8191846, 11/30/2017, Location H33, Serial #8191848, 11/30/2017, Location H34,
Serial #8907736, 06/01/2017
SSC Risk Rankings and Work Practice Rankings, NEI 07-07 Ground Water Impact Risk Score
2016 and 2017 Ground Water Monitoring Well Results Excel Spreadsheet
Florida Department of Health Environmental Laboratory Cross Check Results Performed by
Analytics, Inc. 11/04/2016 and 12/22/2016.
St. Lucie Plant 2016 Meteorological Tower Joint Frequency Distributions for 10 and 58 Meter
Tower
WO 40460916 01, U0: FSAR/PM0 110/Met Tower Semiannual Calibrations, Dated 03/31/17
WO 40496427 01, U0: FSAR/PM0 110/Met Tower Semiannual Calibrations, Dated 10/11/17
2017 Annual Review of DOH Bureau of Radiation Control, Environmental Radiation Control,
Radiological Environmental Monitoring Program (REMP), 01/02/2018
CAP Documents
AR 02172180
AR 02138430
AR 02183034
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling,
Storage, and Transportation
Procedures, Guidance Documents, and Manuals
20025, Process Control Program, Rev. 16
CS-OP-PR-008-161049, Setup, Operation, and Dewatering Using Energy Solutions Self-
Engaging Dewatering System Fillhead at St. Lucie, Rev. 0
Energy Solution s Cask Book for Model 14/210 and 14-215H, Rev. 19
HP-47, Classification of Radioactive Waste Material for Land Disposal, Rev. 28C
HP-49, Dewatering Radioactive Bead Resins, Rev. 15
PI-AA-104-1000, Condition Reporting, Rev. 16
RP-AA-107-1002, Requirements for Radioactive Materials Stored Outdoors, Rev. 7
RP-AA-108-1002, Shipment of Radioactive Material, Rev. 10
RP-AA-108-1003, Radioactive Materials Surveys for Shipment, Rev. 6
RP-AA-108-1004, Packaging Radioactive Materials for Shipment, Rev. 2
RP-SL-107-2001, Transfer of Radioactive Bead Resins, Rev. 3
Records and Data Reviewed
2013 St. Lucie U1 SRT Resin 10 CFR 61 Analysis, 10/9/15
2013 St. Lucie Waste Water Ion Exchanger Resin WIX 10 CFR 61 Analysis, 4/5/14
2016 St. Lucie U2 SRT Resin 10 CFR 61 Analysis, 12/14/16
2018 St. Lucie Dry Active Waste 10 CFR 61 Analysis, 1/16/18
GEL Laboratories, LLC, 10 CFR Part 50/61 Certificate of Analysis, 160-0024 U1 SRT Resin,
5/24/16
Outdoor Container Logs, 8/17 and 11/17
Shipping Record No.16-081, SCO-II, DAW (AREVA Tooling), 10/24/16
Shipping Record No.17-024, LSA-II, U1 SRT and WIX (Depleted Bead Resin), 2/16/17
Shipping Record No.17-070, LSA-II, DAW (Trash), 9/6/17
Shipping Record No.18-029, LSA-II, DAW (Laundry), 3/20/18
Shipping Record No.18-031, LSA-II, DAW (Code Safety Valves), 3/22/18
CAP Documents
AR 02178184
AR 02205825
AR 02238601
St. Lucie Nuclear Oversight Report, Radiation Protection and Rad Waste, RPT # PSL 16-002,
5/26/16
71151: PI Verification Inspection
Procedures, Guidance Documents and Manuals
LI-AA-100-10003, NRC Performance Indicator, Rev. 1
RP-AA-103-1002, High Radiation Area Controls, Rev. 8
RP-AA-102-1001, Area Radiological Surveys, Rev. 4
RP-AA-103-1001, Posting Requirements for Radiological Hazards, Rev. 4
Records and Data Reviewed
ADM-25.02, RETS/ODCM Radiological Effluent Occurrence, Data Sheet 1, 1st through 4th
Quarters 2017
Plant Saint Lucie Electronic Dosimeter Alarm Records, April 1, 2017 - December 31, 2017
CAP Documents
AR 02204181
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
May 1, 2018
Mr. Mano Nazar
President and Chief Nuclear Officer
Nuclear Division
Florida Power & Light Co.
Mail Stop: EX/JB
700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT: ST. LUCIE PLANT - NUCLEAR REGULATORY COMMISSION INTEGRATED
INSPECTION REPORT 05000335/2018001 AND 05000389/2018001
Dear Mr. Nazar:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at your St. Lucie Plant Units 1 and 2. On April 19, 2018, 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.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
The finding did not involve a violation of NRC requirements.
If you disagree with the finding not associated with a regulatory requirement in this report, you
should provide a response within 30 days of the date of this inspection report, with the basis for
your disagreement, to the
- U.S. Nuclear Regulatory Commission, ATTN: Document Control
Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region II; and
the NRC resident inspector at the St. Lucie Plant.
M. Nazar 2
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 Ryan C. Taylor Acting for/
Randall
- A. Musser, Chief
Reactor Projects Branch 3
Division of Reactor Projects
Docket Nos.: 50-335, 50-389
Enclosure:
and 05000389/2018001
cc Distribution via ListServ
OFFICE RII/DRP RII/DRP RII/DRS RII/DRS RII/DRS RII/DRS
NAME TMorrissey SRoberts AButcavage WPursley JPanfel JRivera
DATE 4/18/18 4/20/18 4/19/18 4/19/18 4/20/18 4/19/18
OFFICE RII/DRP RII/DRP RII/DRP
NAME AWilson LPressley RMusser /RA RCT for/
DATE 4/19/18 4/20/18 5/1/18
U.S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos: 50-335, 50-389
Report Nos: 05000335/2018001, 05000389/2018001
Enterprise Identifier: I-2018-001-0062
Licensee: Florida Power & Light Company (FPL)
Facility: St. Lucie Plant, Units 1 and 2
Location: 6501 South Ocean Drive
Jensen Beach, FL 34957
Dates: January 1, 2018 through March 31, 2018
Inspectors:
- T. Morrissey, Senior Resident Inspector
- S. Roberts, Resident Inspector
- W. Pursley, Health Physicist (Sections 71124.01, 71124.07 and 71151)
- A. Butcavage, Reactor Inspector (Section 71111.08)
Approved by:
- R. Musser, Chief
Reactor Projects Branch 3
Division of Reactor Projects
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. NRC and self-
revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations
Improper Evaluation of LCV-9005 position setpoints Leads to AFAS
Cornerstone Significance Cross-cutting Aspect Report
Section
Mitigating Green Finding None 71153
Systems FIN 05000389/2018001-01
Closed
A self-revealed Green finding was identified when the licensee failed to properly evaluate a
discrepancy between A and B feedwater bypass level control valve positions, as required by
licensee procedures PI-AA-205, Condition Evaluation and Corrective Action, and PI-AA-100-
1008, Condition Evaluation.
Additional Tracking Items
Type Tracking number Title Report Section Status
Licensee 05000389/2017-004-00 Automatic Reactor 71153 Closed
Event Trip due to
Report Turbine Control
(LER) System
Malfunction
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On March 11,
2018, the control room operators commenced a planned power reduction and manually tripped
the reactor from 25 percent RTP on March 12, 2018 to start a planned refueling outage. Unit 1
was shutdown in Mode 6 at the conclusion of the inspection period.
Unit 2 operated at or near 100 percent 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
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending adverse cold weather conditions below
degrees Fahrenheit on January 4-5, 2018.
71111.04 - Equipment Alignment
Partial Walkdown (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) Unit 1, 1B high pressure safety injection (HPSI) train with 1A HPSI train out of service
(OOS) for planned maintenance on January 9, 2018
(2) Unit 2, 2A and 2B auxiliary feed water (AFW) trains while the 2C AFW train was OOS for
planned and emergent maintenance on January 17, 2018
(3) Unit 2, 2A emergency diesel generator (EDG) while 2B EDG was OOS for an extended
planned outage on January 23-25, 2018
71111.05AQ - Fire Protection Annual/Quarterly
Quarterly Inspection (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) Unit 2, cable spreading room on January 14, 2018
(2) Unit 2, spent fuel handing building on February 7, 2018
(3) Unit 1, 1B EDG room on February 23, 2018
(4) Unit 1, reactor containment building (RCB) 62 foot (ft.) elevation on March 21, 2018
(5) Unit 1, RCB 18 ft. and 23 ft. elevations on March 21, 2018
Annual Inspection (1 Sample)
The inspectors evaluated fire brigade performance during two separate drills on January 12,
2018 and February 5, 2018. In addition, the inspectors evaluated fire brigade performance
on March 23, 2018, when responding to a Unit 1 fire resulting from a degraded welding
cable that was extinguished prior to arrival of the fire brigade. The inspectors also evaluated
the licensees self-contained breathing apparatus (SCBA) program including storage,
training, expectations for use, and maintenance.
71111.06 - Flood Protection Measures
Internal Flooding (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the Unit 2 reactor
auxiliary building (RAB) -0.5 ft. elevation on February 27, 2018.
71111.07A - Heat Sink Performance (1 Sample)
On March 14, 2018 the inspectors evaluated the readiness and availability of Unit 1, 1A
component cooling water (CCW) heat exchanger (HX) by verifying periodic maintenance
methods outlined in Electric Power Research Institute (EPRI) HX performance monitoring
guideline, NP-7552, were utilized.
71111.08 - Inservice Inspection Activities (1 Sample)
The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the
following examinations from March 19 - 23, 2018:
(1) Magnetic Particle (MT)
a) Work Order 40497052-02, Weld Traveler No. 02029-018683, Weld Number 02029,
ASME Code Class 3. Pipe to Pipe, Intake Cooling Water pressure boundary weld.
(reviewed)
b) Work Order 40497052-02, Weld Traveler No. 02030-18646, Weld Number 02030,
ASME Code Class 3, Pipe to Pipe, Intake Cooling Water pressure boundary weld.
(reviewed)
c) Report No. PSL-1-MT-18-002, Summary No. SL1-010920, Component Id: RV
Support @180 Degrees (B Hot Leg), ASME Code Class 1. (reviewed)
(2) Ultrasonic (UT)
a) Summary No. 001500, Reactor Vessel Upper Shell to Intermediate Shell,
Component Id: 8-203, Weld W02, Flaw No. 2, ASME Class 1, March 22, 2018
(observed Level III review of UT data)
b) Flaw Evaluation Summary Sheet, Weld W02, Flaw No. 2, ASME Class 1,
November 4, 2008 (Observed/Discussed Level III review comparison to previous
2008 UT data)
c) Summary No. 002300, Reactor Vessel Inlet Nozzle at 120 Degrees, Nozzle to Shell
Weld from Vessel Inside Diameter, Component Id: 4-205-A, Weld W27, Flaw No. 2,
ASME Class 1, March 22, 2018 (observed Level III review of UT Data)
d) Flaw Evaluation Summary Sheet, Weld W27, Flaw No. 2, ASME Class 1,
November 4, 2008 (Observed/Discussed Level III review/comparison to previous
2008 UT data)
(3) Visual (VT-3)
a) VT Data Sheet No. 4.15-001, Reactor Pressure Vessel Upper Head, Bare Metal
Visual Examination, In-Core Instrumentation Penetration No. 3, March 27, 2018
(reviewed)
b) Report No. PSL-1-VT-18-001, Summary No. SL1-010910, Component Id: RV
Support @180 Degrees (B Hot Leg), ASME Code Class 1. (reviewed)
The Inspectors evaluated the licensees boric acid control program performance and
performed walk-down inspections of the reactor containment building.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification - 71111.11Q (1 Sample)
On January 29, 2018, the inspectors observed and evaluated a licensed operator crew during
an evaluated emergency plan evaluation on the control room simulator. The simulated scenario
included an excessive steam demand, a manual reactor trip, and failure of engineered safety
features activation system (ESFAS) which caused the control team to manually initiate
emergency boration. A fire alarm in containment resulted in an Unusual Event emergency
classification which required a simulated notification to the State of Florida and the NRC.
Operator Performance - 71111.11Q (1 Sample)
The inspectors observed and evaluated operator performance during a shut down and cool
down of Unit 1 to support a planned refueling outage on March 11-12, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (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) 2244819, 2C AFW steam admission valve K822 relay failure
(2) Unit 2, AR 2232840, A train main feed isolation valve (MFIV) failure
Maintenance Rule (a)(3) periodic assessment (1 Sample)
The inspectors reviewed the licensees Maintenance Rule periodic assessment as
documented in AR 2238173 on January 25, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) Unit 2, elevated risk with 2C AFW pump OOS to replace an electrical relay and 2A CCW
HX OOS for planned cleaning on January 17-18, 2018
(2) Unit 2, elevated risk due to 2B EDG OOS for an extended planned outage on
January 22-25, 2018
(3) Unit 1, elevated risk due to 1A HPSI pump OOS for planned maintenance on
January 19, 2018
(4) Unit 2, elevated risk due to 2A HPSI pump, 2A low pressure safety injection pump (LPSI)
OOS for planned maintenance on February 5, 2018
(5) Unit 1, yellow risk shutdown safety assessment with the reactor coolant system (RCS) at
lowered inventory to support reactor vessel head removal on March 14-16, 2018
71111.15 - Operability Determinations and Functionality Assessments (6 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) Unit 2, ARs 2226700 and 2242181 documenting a 2B EDG lube oil leak on
January 24, 2018
(2) Unit 2, AR 2245486, control room envelope negative differential pressure while in
recirculation mode on February 8, 2018
(3) Unit 1, AR 2249125, control room outside air intake radiation monitors (RIS-26-84, -85)
did not cause a Fail Alarm during testing on February 21, 2018
(4) Unit 1, AR 2252656, shield building ventilation high efficiency particulate air filter test
results just below specification on March 7, 2018
(5) Unit 1, ARs 2253859, 2253860, 1A EDG did not meet surveillance acceptance criteria
on March 13, 2018
(6) Unit 1, AR 2255986, refueling water tank linear stress cracks on March 26, 2018
71111.18 - Plant Modifications (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
Engineering change (EC) 290453, auxiliary feedwater actuation system (AFAS) relay
modification February 13, 2018
71111.19 - Post Maintenance Testing (5 Samples)
The inspectors evaluated the following post maintenance tests:
(1) Unit 2, 2-OSP-69.24, Engineered Safeguards Relay Test, Train A, after replacing a
failed relay for HPSI valve HCV-3627 in accordance with work order (WO) 40580192 on
January 3, 2018
(2) Unit 2, WOs 40521474 and 40521492, post-maintenance test instructions after
performing 2C AFW pump trip and throttle valve lubrication and spring testing in
accordance with the same WOs on January 8, 2018
(3) Unit 2, 2-OSP-99.08A, A Train Quarterly Non Check Valve Cycle Test, after replacing
the 2A CCW HX temperature control valve per WO 40571871 on January 19, 2018
(4) Unit 2, 2-SMI-09.40, Auxiliary Feedwater Actuation System Actuation Relay Test, after
rewiring a relay per WO 40582284 on January 17, 2018
(5) Unit 1, 1-OSP-99.08B, B Train Quarterly Non Check Valve Cycle Test, after performing
preventative maintenance on 1B LPSI suction valve V3432 per WO 40474746, on
January 26, 2018
71111.20 - Refueling and Other Outage Activities (Partial Sample)
The inspectors evaluated Unit 1 refueling outage (SL1-28) activities from March 12, 2018
to March 31, 2018. The inspectors completed inspection procedure Sections 03.01.a,
03.01.b, and 03.01.c. The inspectors partially completed the remaining inspection
procedure sections. These inspection procedure sections will be completed during the
second quarter of 2018.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (3 Samples)
(1) Unit 2, 2-OSP-59.01A, 2A Emergency Diesel Generator Monthly Surveillance, (fast
start) on January 8, 2018
(2) Unit 2, 2-SME-09.40, Auxiliary Feedwater Actuation System Actuation Relay Test, on
January 16, 2018
(3) Unit 1, 1-OSP-69.13A, ESF Staggered 36 Month Surveillance For SIAS/CIS/CSAS -
Train A, on March 13, 2018
In-service (2 Samples)
(1) Unit 2, 2-OSP-03.06B, 2B Low Pressure Safety Injection Pump Code Run, on
February 20, 2018
(2) Unit 1, 1-OSP-03.06A, 1A Low Pressure Safety Injection Pump Code Run, on
March 7, 2018
Containment Isolation Valve (1 Sample)
Unit 1, 1-OSP-68.02, Local Leak Rate Test (penetration 56) on March 19, 2018
71114.06 - Drill Evaluation
Emergency Planning Drill (1 Sample)
On January 10, 2018, the inspectors evaluated an emergency response drill that included
a major loss of control room annunciators, a steam generator tube leak, loss of condenser
vacuum, a manual reactor trip, a steam generator tube rupture, and a stuck open main
steam safety valve.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (1 Sample)
The inspectors evaluated radiological hazards assessments and controls.
Instructions to Workers (1 Sample)
The inspectors evaluated worker instructions.
Contamination and Radioactive Material Control (1 Sample)
The inspectors evaluated contamination and radioactive material controls.
Radiological Hazards Control and Work Coverage (1 Sample)
The inspectors evaluated radiological hazards control and work coverage.
High Radiation Area and Very High Radiation Area Controls (1 Sample)
The inspectors evaluated risk-significant high radiation area and very high radiation area
controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
The inspectors evaluated radiation worker performance and radiation protection technician
proficiency.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (1 Sample)
The inspectors evaluated the licensees radioactive gaseous and liquid effluent treatment
systems during plant walkdowns.
Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)
The inspectors evaluated the licensees gaseous and liquid effluent monitor instrument
calibration and testing.
Sampling and Analyses (1 Sample)
The inspectors evaluated radioactive effluent sampling and analysis activities.
Instrumentation and Equipment (1 Sample)
The inspectors evaluated radioactive effluent instrumentation and equipment.
Dose Calculations (1 Sample)
The inspectors evaluated dose calculations.
71124.07 - Radiological Environmental Monitoring Program
Site Inspection (1 Sample)
The inspectors evaluated the licensees radiological environmental monitoring program.
Groundwater Protection Initiative Implementation (1 Sample)
The inspectors evaluated the licensees groundwater monitoring program.
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
Radioactive Material Storage (1 Sample)
The inspectors evaluated the licensees radioactive material storage.
Radioactive Waste System Walkdown (1 Sample)
The inspectors evaluated the licensees radioactive waste processing facility during plant
walkdowns.
Waste Characterization and Classification (1 Sample)
The inspectors evaluated the licensees radioactive waste characterization and
classification.
Shipment Preparations (1 Sample)
The inspectors evaluated the licensees radioactive material shipment preparation
processes.
Shipment Records (1 Sample)
The inspectors evaluated the licensees non-excepted package shipment records.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification (8 Samples)
The inspectors verified the following licensee performance indicators submittals for the periods
listed below.
(1) Radiological Effluent TS/ODCM Radiological Effluent Occurrences from April 1, 2017,
through December 31, 2017
(2) Occupational Exposure Control Effectiveness from April 1, 2017, through
December 31, 2017
(3) Unit 1, Unplanned Scrams per 7000 Critical Hours from January 1, 2017, through
December 31, 2017
(4) Unit 2, Unplanned Scrams per 7000 Critical Hours from January 1, 2017, through
December 31, 2017
(5) Unit 1, Unplanned Power Changes per 7000 Critical Hours from January 1, 2017,
through December 31, 2017
(6) Unit 2, Unplanned Power Changes per 7000 Critical Hours from January 1, 2017,
through December 31, 2017
(7) Unit 1, Unplanned Scrams With Complications from January 1, 2017, through
December 31, 2017
(8) Unit 2, Unplanned Scrams With Complications from January 1, 2017, through
December 31, 2017
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issue. The issue was selected due to its repetitive nature.
2B CCW HX (ARs 2216036 and 2225449), which detailed actions taken to address tube
leakage most likely caused by a combination of erosion and corrosion as a result of a stuck
shell on the inside of a tube.
71153 - Follow-up of Events and Notices of Enforcement Discretion
Licensee Event Reports (1 Sample)
The inspectors evaluated the following Licensee Event Report (LER) which can be
accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
LER 05000389/2017-004-00, Automatic Reactor Trip due to Turbine Control System
Malfunction, on October 26, 2017
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation (1 Sample)
During the week of January 29, 2018, the inspectors, through direct observation and
independent evaluation, observed the loading of dry shielded cask (DSC)-084 from the
Unit 2 spent fuel pool. The inspectors verified the cask loading activities were performed
in a safe manner and in compliance with approved procedures. Based on direct
observation and review of selected records, the inspectors verified the licensee had
properly identified each fuel assembly placed in DSC-084. Additionally, through direct
observation, the inspectors verified the licensee had properly placed DSC-085 in the
Independent Spent Fuel Storage Installation (ISFSI). The inspectors also observed
activities associated with the transport and storage of casks, loading of spent fuel in
casks, vacuum drying and seal welding activities, and the heavy lifts to remove the
casks from the spent fuel pool and placing them in the cask handling facility.
INSPECTION RESULTS
Improper Evaluation of LCV-9005 Position Setpoints Leads to AFAS
Cornerstone Significance Cross-cutting Aspect Report
Section
Mitigating Green Finding None 71153
Systems FIN 05000389/2018001-01
Closed
A self-revealed Green finding was identified when the licensee failed to properly evaluate a
discrepancy between A and B feedwater bypass level control valve positions, as required by
licensee procedures PI-AA-205, Condition Evaluation and Corrective Action, and PI-AA-100-
1008, Condition Evaluation.
Description:
On November 19, 2013, during reactor startup activities, feedwater bypass valves, A (LCV-
9005) and B (LCV-9006), were found to be operating at different throttle positions while
maintaining their respective steam generator water levels. Valves LCV-9005 and 9006 were
both originally installed in April 1978. LCV-9005 was replaced in 1994, with an equivalent
valve, due to obsolescence. The original valve had a full open stroke length of 1.5 inches
(in.), while the new equivalent valve had a full open stroke length of 2 in. to provide the
same flow as the original valve. When installed, LCV-9005 was set up to limit its stroke
length to 1.5 in., matching the replaced valve, and the associated drawings were never
revised to show that the new valve had a full 2 in. open stroke length. In 2009, the
distributed control system (DCS) was installed utilizing these drawings and was setup under
the assumption that both valves, LCV-9005 and LCV-9006, were the same model valves
and stroke lengths.
The DCS system was designed to provide a signal to throttle the feedwater bypass valves
following a reactor trip to 20 percent open to provide approximately 5 percent feed flow in
order to recover steam generator water levels utilizing main feedwater. During Unit 2
startup activities in November 2013, the licensee noted a discrepancy in the valve positions
for LCV-9006 and LCV-9005 when they were providing steam generator water level control.
The licensee placed the issue in the corrective action program under Action Request (AR)
21720 and determined that it was necessary to evaluate a revision of the LCV-9005 DCS
setpoint, which was accomplished by an engineering condition evaluation under AR
25428. The engineering condition evaluation was inadequate in that it failed to recognize
the differences in the two different model valves, and therefore failed to provide adequate
corrective actions to address performance issues associated with these differences.
The final recommendation from AR 1925428 was that the current LCV-9005 setting did not
impose any risk to the plant operation, as the 2A steam generator level had been within
acceptable range with no control room alarm observed. Therefore, no setpoint change was
required at that point.
On October 26, 2017, following a Unit 2 trip, LCV-9005 was sent a digital DCS demand
signal to be 20 percent open. Since the valve was locally set to have a maximum stroke of
1.5 in. instead of 2 in. open, the actual flow through the valve was less than 5 percent. This
resulted in flow lower than needed to maintain 2A steam generator level, and caused level
to lower, which eventually resulted in an actuation of the A train auxiliary feedwater
actuation system (AFAS).
Corrective Action(s): The licensee implemented corrective actions to: 1) properly set up
LCV-9005 in order for it to have a full stroke length of 2 inches so that it could provide the
required feedwater flow and, 2) update associated drawings to include correct stroke
lengths.
Corrective Action Reference(s): This issue was entered into the licensees CAP as AR
232869
Performance Assessment:
Performance Deficiency: The failure to properly evaluate a discrepancy between the A and
B feedwater bypass level control valve positions, as required by licensee procedures PI-
AA-205, Condition Evaluation and Corrective Action, and PI-AA-100-1008 Condition
Evaluation, was a performance deficiency.
Screening: The inspectors determined that the performance deficiency was more than
minor because it was associated with the Mitigating Systems cornerstone attribute of human
performance and adversely affected the cornerstone objective of ensuring the availability,
reliability, and capability of systems that respond to initiating events to prevent undesirable
consequences (i.e., core damage). Specifically, the licensee conducted an ineffective
condition evaluation of a noticeable difference between the A and B feedwater bypass
level control valve positions, discovered during a Unit 2 reactor startup on November 19,
2013. This failure of their CAP, to ensure this issue was adequately resolved, resulted in
inadequate feed flow to the 2A steam generator, following a Unit 2 trip in 2017, which
resulted in a lowered steam generator level and caused an actuation of the A train AFA
- S.
Significance: Using Inspection Manual Chapter (IMC) 0609, Attachment 4, Initial
Characterization of Findings, Table 2, the finding was determined to affect the Mitigating
Systems cornerstone due to degradation to main feedwater which affected decay heat
removal. IMC 0609, Appendix A, The Significance Determination Process (SDP) for
Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, was used to
further evaluate this finding. The finding screened as Green because the deficiency did not
affect the design or qualification of a mitigating structure, system, and component (SSC)
and the SSC maintained its operability or functionality. This finding did not present an
immediate safety concern and there were no compensatory measures in place while the
licensees long-term corrective actions were being implemented.
Cross-cutting Aspect: No cross cutting aspect was assigned to this finding because the
inspectors determined the finding did not reflect present licensee performance.
Enforcement:
The inspectors did not identify a violation of regulatory requirements associated with this
finding.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On January 26, 2018, the inspectors presented the radiation protection inspection results to
Mr. DeBoer, Site Director, and other members of the licensee staff.
On March 23, 2018, the inspectors presented the inservice inspection and radiation protection
results to Mr. DeBoer, Site Director, and other members of the licensee staff.
On April 19, 2018, the inspector presented the quarterly resident inspector inspection results to
Mr. DeBoer and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01: Adverse Weather Protection
0-NOP-99.06, Cold Weather Preparations
71111.04: Equipment Alignment
1-NOP-03.11, High Pressure Safety Injection Initial Alignment
2-NOP-09.11, Auxiliary Feedwater System Initial Alignment
2-NOP-59.01A, 2A Emergency Diesel Generator Standby Alignment
71111.05: Fire Protection
ADM-0005729, Fire Protection Training, Qualification and Requalification
ADM-19.02, Pre-Fire Plan Standard Operating Procedure
71111.06: Flood Protection Measures
2-AOP-24.01, RAB Flooding
WO 40497180, ESFAS Sump LS-06-1B Calibration
WO 40502838, ESFAS Sump LS-06-1A Calibration
71111.08 Inservice Inspection Activities
Procedures:
ADM-17.29, Reactor Vessel Internals Aging Management Program, Rev. 6
CY-SL-108-0002, High Activity in a Steam Generator, Rev. 2
ER-AP-116-1000, Nuclear Fleet Administrative Procedure, Boric Acid Corrosion Control
Program, Rev. 2
NDE-4.15, Manual Examination Procedure, Component, Support & Inspection, Visual
Examination (VE), ASME Section XI, Code Case N-722-1 and N-729-4, 3/12/18
54-ISI-364-008, NDE Procedure, Remote Underwater Visual Examination of Reactor Pressure
Vessels, Vessel Internals, and Components in Pressurized Water Reactors in Accordance
with Section XI. 2/8/18
54-ISI-801-003, Nondestructive Examination Procedure, Automated UT of PWR Vessel Shell
Welds, 9/4/15
Drawings:
8770-G-068, Florida Power and Light St Lucie Plant, General Arrangement, Reactor Building
Sections, Sheet 2, Rev. 19
8770-G-365, Florida Power and Light Hutchinson Island Plant, El. 18, Reactor Containment
Building Sections El. 18 0 , Sheet 2, Rev. 57
E-233-496, Ebasco Services, General Arrangement Elevation, Reactor Vessel, Rev. 6
E-233-496, Ebasco Services, As-Built Reactor Vessel, Rev 4
CB Elev. OD (PSL-1), Outside Diameter, Plant St. Lucie, Unit-1, Core Barrel Elevation Plant
Saint Lucie-1 (Sketch), Rev. 1
CB Elev. (PSL-1) Shroud Plate Numbering (Sketch), Rev. 3
RPV-CB Plan (PSL-1), Core Barrel in Reactor Vessel (Sketch), Rev. 2
UGFAP (PSL-1), Upper Internals Assembly Fuel Alignment Plate Bottom View (Sketch), Rev. 1
UGS (PSL-1), Upper Guide Structure (Sketch), Rev.1
01-001-G, Florida Power and Light, St. Lucie Unit-1, Reactor Pressure Vessel Upper and Lower
Internal Assembly (Sketch), Rev. 2
Self-Assessments:
2079327, Quick Hit, Department Assessment Report, St Lucie Units 1 & 2, Boric Corrosion
Control Program (BACCP), 6/28/16
Work Orders/Work Requests:
289976-01, SL1-28, Att. 1, Thimble Inspection, 3/30/18
40497052, SL1, Intake Cooling Water (CW-78) West Shear Wall Penetration Replacement,
3/23/28
40513412, SL1, Rx Vessel-Reactor Vessel Internals Program (MRP-227) Inspections SL1-28,
2/1/18
40516114, SL1, ISI Reactor Vessel, 3/14/18
289976, SL1, Inspect ICI Thimble Zircaloy Section AR 1845589, 3/20/18
Action Requests:
AR-01845589, Engineering Review of Westinghouse Letter FPL-13-5, Operating Experience for
In-Core Instrumentation Thimble Failure at a similar facility, 2/5/13
AR-02254768, Thimble in ICI location W-4, Through Wall Wear, 3/19/18
AR-02253932, Pipe Support Snubber 121 Found Disconnected from End Attachment, 3/13/18
AR-02199850, Wet Brown Boric Acid Apparent on 1B Charging Pump Plunger, 4/19/17
AR-02186650, Valve 03993, Active Boric Acid Leak at Packing, 2/20/17
AR-02209017, Valve 5203, Active Boric Acid Leak on Downstream Side, 6/7/2017
AR-02255865, Linear Indications on Core Support Barrel-MRP-227 Exams, 3/23/18
Miscellaneous Documents:
AIM 160810113-2Q-3, Condition Monitoring and Operational Assessment for the St. Lucie Unit
Steam Generators Based on Eddy Current Examination End of Cycle 26, October 2016,
January, 2017
EC 280215, Snubber Acceptance Testing Criteria, Rev.19
FP&L, Under Vessel Photograph No. 8, Reactor Support Column, 3/22/18
FP&L, Under Vessel Photograph No. 11, Reactor Support Column, 3/22/18
FP&L, Under Vessel Photograph No. 15, Reactor Support Column, 3/22/18
Framatome Visual Inspection Summary List, Prior to performing Exams, 3/16/18
Intertek Letter, Review of Operation and degradation assessments for St. Lucie Unit-1 Steam
Generators for Cycle 27, 11/6/17
LTR-AMLR-18-22 Disposition of Indications Observed in the Core Support Barrel at SL1,
(Westinghouse, Ref: 18-36) 3/30/18
MRP-228, Electric Power Research Institute, Materials reliability Program, Inspection Standard
for Pressurized Water Reactor Internals, 2015 Update, Rev. 2
NDE Personnel Qualification and Certification Records for
- M. Hacker, D. Langenfeld
PSL-ENG-LRAM-15-002, Reactor Vessel Internals Inspection Program-License Renewal Basis
Document, Rev.4
Report Number 1101242.410, Piping Stress Analysis Report for the Auxiliary Spray Piping
Calculation 3900001-004, St Lucie Nuclear Power Plant Unit-1, 11/4/11
St Lucie Unit-1, Fourth In-Service Inspection Program Plan, Revision 5, 3/5/18
St Lucie Unit-1, Fifth In-Service Inspection Program Plan, Revision 0, 2/10/18
54-ISI-364-008, NDE Procedure, Remote Underwater Visual Examination of Reactor Pressure
Vessels, Vessel Internals, and Components in Pressurized Water Reactors in Accordance
with Section XI. 2/8/18
54-ISI-801-003, Nondestructive Examination Procedure, Automated UT of PWR Vessel Shell
Welds, 9/4/15
71111.11: Licensed Operator Requalification Program and Licensed Operator
Performance
2-AOP-01.10, Pressurizer Pressure and Level
2-AOP-01.08, Reactor Coolant System Leakage
2-AOP-08.01, Steam Leak
2-AOP-22.01, Rapid Down Power
2-AOP-100.01, Response to Fire
2-EOP-01, Standard Post Trip Actions
2-EOP-05, Excess Steam Demand Event
EPIP-01, Classification of Emergencies
EPIP-02, Duties and Responsibilities of the Emergency Coordinator
EPIP-08, Offsite Notifications and Protective Action Recommendations
1-GOP-123, Turbine Shutdown - Full Load To Zero Load
1-EOP-01, Standard Post Trip Actions
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
OM-AA-101-1000, Shutdown Risk 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-01.03, Draining RCS
1-NOP-01.05, Filling and Venting RCS
1-NOP-02.02, Charging and Letdown
ADM-09.26, Shutdown Cooling Controls
1-GOP-305, Reactor Plant Cooldown - Hot Standby To Cold Shutdown
1-GOP-365, Refueling Sequence Guidelines
1-NOP-67.02,Spent Fuel Handling Machine Operation
1-NOP-67.04, Refueling Machine Operation
0-NOP-67.05, Refueling Operation
71111.22: Surveillance Testing
ADM-29.02, ASME Code Testing of Pumps and Valves
71124.01: Radiological Hazard Assessment and Exposure Controls
Procedures, Guidance Documents, and Manuals
ADM-05.06, Control of Radioactive Material, Revision (Rev.) 3
HPP-1, Preparing Radiation Work Permits, St. Lucie Plant, Rev. 40
HPP-41, Movement of Material and Equipment, Rev. 38
RP-AA-100, Radiation Protection Administrative Program, Rev. 07
RP-AA-102-1001, Area Radiological Surveys, Rev. 04
RP-AA-103-1001, Posting Requirements for Radiological Hazards, Rev. 04
RP-AA-103-1002, High Radiation Area Controls, Rev. 08
RP-AA-103-1006, Conduct Of Radiological Diving Operations, Rev. 5
RP-AA-107-1002, Requirements for Radioactive Materials Stored Outdoors, Rev. 07
RP-AA-107-1003, Unconditional and Conditional Release of Material, Rev. 04
RP-AA-107-1004, Procedure for Radioactive Source Controls and Leak Checking, Rev. 0
RP-SL-101-1003, Personnel Contamination Monitoring and Decontamination, Rev. 02
Records and Data
RP-AA-107-1004-F02: Source Leak Test and Inventory Form, 1/12/2018
RP-AA-107-1004-F02: Source Leak Test and Inventory Form, 2/12/2018
RP-SL-103-2005, U1 and U2 Spent Fuel Pool Non-SNM Item Inventory Log Sheet, 11/14/17
Air Sample Data Summary Sheet #181-0098, U1 RCB 62 During Filling of Rx Cavity,
03/16/2018
Air Sample Data Summary Sheet #181-0231, U1 RCB Keyway/Under Vessel, 03/22/2018
Air Sample Data Summary Sheet #181-0208, U1 RCB 62 During Core Barrel Move, 03/21/2018
Air Sample Data Summary Sheet #181-0223, U1 RCB Top of Pressurizer During Removal of
Code Safeties, 03/21/2018
Air Sample Data Summary Sheet #181-0151, U1 SFP 62 During Fuel Movement, 03/18/2018
Radiological Work Permit (RWP) 18-1039, Core Support Barrel, Lift Rigs: Remove/Replace. All
Support Work, Rev. 06
RWP-18-1352, Keyway and Beneath the Reactor Vessel Activities, Rev. 01
RWP-18-1410, Pressurizer Code Safetys, Rev. 0
RWP-18-1317, Lower Cavity Survey / Decon Activities, Rev. 0
RWP 18-1112, Remove, Install, Transfer Excore Detector #10 Under Vessel, Rev. 0
Survey PSL-M-20180322-16, HPS-63 U1 RCB Under Rx Vessel Survey/Inspection, 03/22/2018
Survey PSL-M-20161019-26, HPS-63 U1 RCB Under Rx Vessel Survey/Inspection, 10/19/2016
Survey PSL-M-20180318-16, HPS-63 U1 RCB 62 Fuel Movement Dose Rates, 03/18/2018
Survey PSL-M-20180322-7, HPS-11; Core Barrel Lift Rig Verification, 03/22/2018
Survey PSL-M-20180320-33, HPS-11; 62 RCB Down Posting During Core Barrel, 03/20/2018
Survey PSL-M-20180322-5, HPS-64; Code Safetys, 03/22/2018
STL Radiation Protection Plan - SL1-28, 10 Y ISI RX Vessel/Core Support Barrel Lift,
03/19/2018
Corrective Action Program (CAP) Documents
AR 02187400
AR 02191149
AR 02203094
AR 02220303
AR 02254603
71124.06: Radioactive Gaseous and Liquid Effluent Treatment
Procedures and Guidance Documents
1-IMP-26.12, Liquid Radwaste Discharge Process Monitor Functional and Calibration
Instructions, Rev. 13
1-SMI-26.72, Calibration of Plant Vent Stack Radiation Monitor, Rev. 1
2-IMP-26.03, Secondary Calibration of Wide Range Gas Monitors (WRGM), Rev. 13
2-IMP-26.06, Secondary Calibration of Particulate Iodine and Gas (PIG) Monitors, Rev. 13
C-200, Offsite Dose Calculation Manual (ODCM), Rev. 50
CY-SL-102-0025, Determination of Gases, Rev. 3
CY-SL-102-0104, Processing Aerated Liquid Wastes, Rev. 9
CY-SL-102-0105, Processing Gaseous Waste, Rev. 6
CY-SL-104-0112, Determination of Process Radiation Monitor Setpoints, Rev. 9
CY-SL-104-1011, Unit 1 Gaseous Effluent Grab Sampling, Rev. 8
CY-SL-104-2011, Unit 2 Gaseous Effluent Grab Sampling, Rev. 6
CY-SL-108-0003, Alternate Methods for Effluent and Process Radiation Monitors, Rev. 4
EPIP-01, Classification of Emergencies, Rev. 26
Records and Data Reviewed
2015 and 2016 Annual Radioactive Effluent Release Reports
Analytics Inc. Cross Check, 12/22/2016
Gas Release Permit No. G-17-474-B, 1A Gas Decay Tank, 12/13/17
Gas Release Permit No. G-17-473-B, Unit 1 Mini-Purge, 12/13/2017
Liquid Release Permit Nos. L-17-068-B and L-17-069-B, Waste Monitor Tank A
PSL Rx1 EAL DBD, PSL NEI-99-01 EALs, Basis for Radiation Monitor Values Used to Classify
Emergencies, Rev. 3
PSL-ENG-SENS-00-108, Safety Evaluation 2000 FSAR Review, Rev. 1
PSL-ENG-SENS-05-033, Analysis of Acceptability of Anisokinetic Sampling of Main Plant Vent,
FHB Vent, and ECCS Vent Exhaust, Rev. 2
PSL-ENG-SENS-16-002, Unit 1 Ventilation Effluent Radiation Monitors Representative
Sampling, Rev. 0
Unit 1 and Unit 2 System Health Reports, Radiation Monitoring, 2017
Visual Inspection, Leak Test, and Velocity Traverse, Unit 1 Main Stack, 1 HVE-10 (A+B) and 1
HVE-9 (A+B), 09/8/16
Visual Inspection, Leak Test, and Velocity Traverse, Unit 2 Main Stack, 2 HVE-10 (A+B), 2
HVE-9 (A+B) and 2 HVE-16, 2/6/17
WO 40340570-01, RE-6627 Liquid Rad Waste Monitor Calibration, 01/15/16
WO 40471192-01, RE-6627 Liquid Rad Waste Monitor Calibration, 07/06/17
WO 40348630-01, U1 RM-26-13 Plant Vent Stack PIG Calibration, 01/07/16
WO 40478509-01, U1 RM-26-13 Plant Vent Stack PIG Calibration, 08/09/17
WO 40283944-01, RSC-26-1 Stack Exhaust WRGM Channel Calibration, 02/20/15
WO 40405767-01, RSC-26-1 Stack Exhaust WRGM Channel Calibration, 09/07/16
WO 40346919-01, RIM-26-90 Plant Vent Gas WRGM Calibration, 03/02/16
WO 40485932-01, RIM-26-90 Plant Vent Gas WRGM Calibration, 09/01/17
WO 40411588-01, U1 RSC-26-4 Fuel Handling Building PIG Calibration, 11/29/16
CAP Documents
Action Request (AR) 02103930
AR 02121876
AR 02167133
AR 02180001
AR 02205687
AR 02224363
AR 02226671
71124.07: Radiological Environmental Monitoring Program (REMP)
Procedures and Guidance Documents
Sampling Procedure 1, Collection of Air Particulates and Radioiodines, Rev. No. 11
Sampling Procedure 4, Collection of Surface Water, Rev. No. 7
Sampling Procedure 5, Collection of Broadleaf Vegetation, Rev. No. 4
Sampling Procedure 12, Annual Land Use Census, Rev. No. 2
Technical Manual 2, Lower Limits of Detection, Rev. 5
C-200, St. Lucie Plant Chemistry Offsite Dose Calculation Manual, Rev. 50
CY-SL-100-0002, Chemistry Department Groundwater Protection Program, Rev. 5
LI-AA-102-1001, Regulatory Reporting, Rev. 20
Records and Data Reviewed
2015 and 2016 Annual Radiological Environmental Operating Reports St. Lucie Plant Units 1 &
2016 Annual Radioactive Effluent Release Report St Lucie Plant Units & 2
2018 St. Lucie Dry Active Waste 10CFR61 Analysis, 01/16/2018
CFR 50.75(g) documentation, Leak of V06231, Dated 10/27/17
CFR 50.75(g) documentation, Leak of U2 RWST FLEX Connection (AR02203932),
05/08/2017
Air Sampler Flow Calibrations for Location H14, Serial #8191844, 12/01/2017, Location H30,
Serial #8191846, 11/30/2017, Location H33, Serial #8191848, 11/30/2017, Location H34,
Serial #8907736, 06/01/2017
SSC Risk Rankings and Work Practice Rankings, NEI 07-07 Ground Water Impact Risk Score
2016 and 2017 Ground Water Monitoring Well Results Excel Spreadsheet
Florida Department of Health Environmental Laboratory Cross Check Results Performed by
Analytics, Inc. 11/04/2016 and 12/22/2016.
St. Lucie Plant 2016 Meteorological Tower Joint Frequency Distributions for 10 and 58 Meter
Tower
WO 40460916 01, U0: FSAR/PM0 110/Met Tower Semiannual Calibrations, Dated 03/31/17
WO 40496427 01, U0: FSAR/PM0 110/Met Tower Semiannual Calibrations, Dated 10/11/17
2017 Annual Review of DOH Bureau of Radiation Control, Environmental Radiation Control,
Radiological Environmental Monitoring Program (REMP), 01/02/2018
CAP Documents
AR 02172180
AR 02138430
AR 02183034
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling,
Storage, and Transportation
Procedures, Guidance Documents, and Manuals
20025, Process Control Program, Rev. 16
CS-OP-PR-008-161049, Setup, Operation, and Dewatering Using Energy Solutions Self-
Engaging Dewatering System Fillhead at St. Lucie, Rev. 0
Energy Solution s Cask Book for Model 14/210 and 14-215H, Rev. 19
HP-47, Classification of Radioactive Waste Material for Land Disposal, Rev. 28C
HP-49, Dewatering Radioactive Bead Resins, Rev. 15
PI-AA-104-1000, Condition Reporting, Rev. 16
RP-AA-107-1002, Requirements for Radioactive Materials Stored Outdoors, Rev. 7
RP-AA-108-1002, Shipment of Radioactive Material, Rev. 10
RP-AA-108-1003, Radioactive Materials Surveys for Shipment, Rev. 6
RP-AA-108-1004, Packaging Radioactive Materials for Shipment, Rev. 2
RP-SL-107-2001, Transfer of Radioactive Bead Resins, Rev. 3
Records and Data Reviewed
2013 St. Lucie U1 SRT Resin 10 CFR 61 Analysis, 10/9/15
2013 St. Lucie Waste Water Ion Exchanger Resin WIX 10 CFR 61 Analysis, 4/5/14
2016 St. Lucie U2 SRT Resin 10 CFR 61 Analysis, 12/14/16
2018 St. Lucie Dry Active Waste 10 CFR 61 Analysis, 1/16/18
GEL Laboratories, LLC, 10 CFR Part 50/61 Certificate of Analysis, 160-0024 U1 SRT Resin,
5/24/16
Outdoor Container Logs, 8/17 and 11/17
Shipping Record No.16-081, SCO-II, DAW (AREVA Tooling), 10/24/16
Shipping Record No.17-024, LSA-II, U1 SRT and WIX (Depleted Bead Resin), 2/16/17
Shipping Record No.17-070, LSA-II, DAW (Trash), 9/6/17
Shipping Record No.18-029, LSA-II, DAW (Laundry), 3/20/18
Shipping Record No.18-031, LSA-II, DAW (Code Safety Valves), 3/22/18
CAP Documents
AR 02178184
AR 02205825
AR 02238601
St. Lucie Nuclear Oversight Report, Radiation Protection and Rad Waste, RPT # PSL 16-002,
5/26/16
71151: PI Verification Inspection
Procedures, Guidance Documents and Manuals
LI-AA-100-10003, NRC Performance Indicator, Rev. 1
RP-AA-103-1002, High Radiation Area Controls, Rev. 8
RP-AA-102-1001, Area Radiological Surveys, Rev. 4
RP-AA-103-1001, Posting Requirements for Radiological Hazards, Rev. 4
Records and Data Reviewed
ADM-25.02, RETS/ODCM Radiological Effluent Occurrence, Data Sheet 1, 1st through 4th
Quarters 2017
Plant Saint Lucie Electronic Dosimeter Alarm Records, April 1, 2017 - December 31, 2017
CAP Documents
AR 02204181
Enclosure