IR 05000335/2022012
| ML22180A029 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/29/2022 |
| From: | David Dumbacher Division Reactor Projects II |
| To: | Coffey B Florida Power & Light Co |
| References | |
| IR 2022012 | |
| Download: ML22180A029 (14) | |
Text
June 29, 2022
SUBJECT:
ST LUCIE UNITS 1 & 2 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000335/2022012 AND 05000389/2022012
Dear Mr. Coffey:
On May 20, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your St Lucie Units 1 & 2 and discussed the results of this inspection with Mr. Daniel DeBoer, Site Vice President and other members of your staff.
The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations problem identification and resolution program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for problem identification and resolution programs.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.
Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Signed by Dumbacher, David on 06/29/22 David E. Dumbacher, Chief Reactor Projects Branch #3 Division of Reactor Projects Docket Nos. 05000335 and 05000389 License Nos. DPR-67 and NPF-16
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000335 and 05000389 License Numbers: DPR-67 and NPF-16 Report Numbers: 05000335/2022012 and 05000389/2022012 Enterprise Identifier: I-2022-012-0015 Licensee: Florida Power & Light Company Facility: St Lucie Units 1 & 2 Location: Jensen Beach, FL Inspection Dates: May 02, 2022 to May 20, 2022 Inspectors: J. Hamman, Senior Project Engineer C. Kontz, Senior Project Engineer L. Pressley, Reliability and Risk Analyst S. Roberts, Resident Inspector Approved By: David E. Dumbacher, Chief Reactor Projects Branch #3 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at St Lucie Units 1 & 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)
- (1) The inspectors performed a biennial assessment of the effectiveness of the licensees Problem Identification and Resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees Problem Identification and Resolution program in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of the auxiliary feedwater and 125-volt direct current systems. In addition, the inspectors performed a high-level review of the licensees corrective action program related to any aging issues, general corrosion and erosion and environmental qualifications with specific attention given to circuit boards, relays and power supplies.
Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B The inspectors reviewed the effectiveness of the licensees Corrective Action Program (CAP). Specifically, as it related to the ability of the CAP to adequately perform the functions of problem identification, prioritization and evaluation of any issues identified and the subsequent related corrective actions.
This included a review of procedure, PI-AA-104-1000, Condition Reporting and other relevant procedures, and associated CAP documents, (i.e., cause evaluation, and operability determination process).
Inspectors performed in-depth reviews of past and current CAP actions for specific systems (i.e. station batteries and auxiliary feedwater and compared those to the current general condition and overall system health.
Inspectors performed a risk-informed sampling review of root cause and other lower-level cause evaluations. Inspectors also reviewed corrective actions associated with prior NRC violations, findings and observations.
During the inspection period, inspectors observed multiple CAP meetings and licensee staff interactions related to the application of the CAP process. Additionally, inspectors conducted multiple interviews with licensee staff specifically related to corrective actions for the systems selected for in-depth reviews.
The inspectors concluded, that in general: the licensees CAP was effective in identifying problems and entering them in the CAP, and in prioritizing and evaluating those problems commensurate with the safety significance; that site management and staff were actively involved in managing and maintaining the CAP and in fully resolving any identified problems, and; that the licensees CAP complied with the regulatory requirements and self-imposed standards and therefore adequately supported nuclear safety.
Assessment 71152B The inspectors reviewed the licensee's program for obtaining and using operating experience.
This included a review of procedure, PI-AA-102, Operating Experience Program and other relevant procedures, and associated CAP documents. This review included select in-depth reviews from the licensees list of all NRC generic communications (e.g., Information Notices, Generic Letters, etc.) and industry operating experience (OE) documents (e.g., Part 21 reports, vendor information letters, information from other sites, etc.).
The inspectors concluded that the licensees processes for the use of NRC and industry operating experience information were generally effective and complied with all regulatory requirements and licensee standards.
Assessment 71152B Inspectors reviewed the licensees self-assessments and audits programs.
This included a review of procedure, PI-AA-101, Assessment and Improvement Programs and other relevant procedures and licensee documents.
The inspectors concluded that the licensee was generally effective at performing a significant number of relatively critical self-assessments and audits. In addition, the licensee generally evaluated those issues at the appropriate level and prioritized and resolved them commensurate with their safety significance.
Assessment 71152B The inspectors reviewed the licensees safety conscious work environment (SCWE). This included a review of Nuclear Safety Culture Site Leadership Team meeting minutes, procedure, AD-AA-103, Nuclear Safety Culture Program and other relevant procedures and licensee documents.
The inspectors performed interviews with a reasonable sample size and cross-section of St.
Lucie employees and contractors.
In general, the employees interviewed by the inspectors stated that they were willing to raise nuclear safety concerns to their management chain and were both willing and familiar with the multiple means available to enter problems into the CAP.
Inspectors also reviewed the licensees internal programs to monitor the safety culture, which included CAP trending, the employee concerns program (ECP), and relevant survey results.
Inspectors concluded that, in general, the licensee appears to have established an adequate safety conscious work environment.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On May 20, 2022, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Daniel DeBoer, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Corrective 02423529 02372036 02422566
Action 02423857 02377147 02370748
Documents 02424262 02395828 02380151
2358851 02398481 02381590
2381509 02404036 02399463
2413519 02404285 02402496
2415359 02404416 02407060
2416187 02411677 02419630
2369201 02417041 02420540
2355625 02426764 02366489
2358403 02426856 02415359
2368316 02426951 02381509
2368421 02426987 02384319
2388996 02426989 02383050
2377657 02426992 02383373
2417569 02426995 02404894
2381504 02426997 02420302
2359116 02407967
2407252 02147383
2380625 02282775
2425203 02423837
2417840 03423929
2417149 02425923
2357024 02322281
2358155 02356660
2358720 02358833
2362210 02404422
2367409 02413519
Inspection Type Designation Description or Title Revision or
Procedure Date
Corrective 02426764 Control Room Deficiency Log Various
Action Administrative Deficiencies
Documents 02426856 Degraded Pipe Insulation Unit 2 on piping
Resulting from adjacent to V08112, Secondary Root Valve
Inspection For PT-08-3B
2426951 1B Battery Charger AC Power Light
Operations promptly replaced the light bulb.
2426987 2B 125V DC Bus Power Panel Yellow
electrical tape labeling not part of normal
plant labeling applied to circuits located in
the 2B 125V DC Bus Power Panel, 125V DC
BUS POWER DISTRIBUTION PANEL ESS-
2426989 V09726 Fitting Corrosion on a fitting
adjacent to V09726, CHEM INJ TO 2C AFW
PUMP DICH HDR TO 2B S/G/CHECK
No evidence of active leakage
2426992 V09154 Vent Cap Leaking (less than 1
drop/minute) Unit 2 secondary root valve for
PX-09-3B2 V09154 previously identified with
seat leak
2426995 V09124 External Corrosion Isolation Valve
for AFW Pump 2B Discharge
2426997 Degraded pipe insulation on tubing tapping
off downstream of the 1B MFIV, HCV-09-8
2427934 Procedure Change Revision (PCR) for EN-
AA-203-1001, Operability
Determinations/Functionality, to revise
authorized screeners (section 4.2.1) to
reflect PSL SM/SRO screening JB CRs. The
process change has been effective since
2018 (CMP 2291377). PCR is needed to
align with the current process.
Inspection Type Designation Description or Title Revision or
Procedure Date
2428049 NRC Observation: Anonymous Concern
Reporting Plant personnel interviewed were
unfamiliar with current processes for
documenting anonymous concerns.
Additionally, the NRC team identified related
administrative process inconsistencies.
Engineering 295797 CEDMCS Cabinet C2 - Revise 120 VAC 4/8/2021
Changes Logic Power Source UV relays
295961 Channel Assignments for Turbine Trip on 7/26/2021
Reactor Trip Relays
296428 Update PSL-2 USFAR Section 7.6.3.11.2 4/8/2021
per AR 2383050
Miscellaneous 2020 & 2021 - Quarter 1 through Quarter 4
NUCLEAR SAFETY CULTURE SITE
LEADERSHIP TEAM MEETING MINUTES
Control Room Deficiencies WO Schedule
Dates
System Health Report, Unit 1, AFW April 28,
22
System Health Report, Unit 2, AFW April 28,
22
System Health Report, Unit 1, System 50,
25 VDC
AR 02278047, MRFF: MV-09-10 SWITCH
ON RTGB BROKEN WITH AFW FLOW @
117 GPM
System Health Report, Unit 2, System 50,
25 VDC
List of Control Room Deficiencies (historical
and current)
Inspection Type Designation Description or Title Revision or
Procedure Date
Root Cause Evaluation for Unit 2 automatic 1/21/2021
reactor trip due to an unexpected de-
energization of the 480V motor control
center 2B2
278047 MRFF: MV-09-10 SWITCH ON RTGB
BROKEN WITH AFW FLOW @ 117 GPM
278047 Equipment Failure Investigation
282775 Perform an MRFF IAW ER-AA-100-2002-
F01 for 2C AFW PP
282775 Equipment Failure Investigation
EVAL-PSL-03b-02442 (a)(1) LPSI System
EVAL-PSL-11-02643 (a)(1) Review Heater Drains and Vents
System
EVAL-PSL-18b-02382 (a)(1) Instrument Air
EVAL-PSL-25a-02642 (a)(1) Risk Significant HVAC
EVAL-PSL-66-02684 (a)(1) Control Element Drive Mechanism
WO 40627600 U1 AFW A-Train WO 40627600,
Components Requiring Inspection for
License Renewal Walkdown Report
Operability 02417041
Evaluations 02417149
2417840
Procedures 0-CME-50.20 REPAIR OF LCR / LCY TYPE BATTERY 1
COVERS
0-SME-50.06 SAFETY RELATED 125 VDC SYSTEM 17, 20
MONTHLY MAINTENANCE
0-SME-50.11 SAFETY RELATED 125 VDC SYSTEM 5
QUARTERLY MAINTENANCE
0-SME-66.04 Inspection of the Reactor Trip Switchgear 10
(RTTSG) Breakers
EN-AA-106 RENEWED LICENSE PROGRAM 8
EN-AA-203-1001 OPERABILITY DETERMINATIONS / 38
EN-AA-206 Renewed License Process 13
Inspection Type Designation Description or Title Revision or
Procedure Date
ENG-CSI-XCI-100 EXTERNAL CORROSION (XCI) 2
MONITORING PROGRAM FOR
INSULATED PIPING FOR PSL AND PTN
ER-AA-100-2002 MAINTENANCE RULE PROGRAM 12
ADMINISTRATION
ER-AA-201-2002 SYSTEM PERFORMANCE MONITORING 7
MA-AA-101-1000-F01 FME Risk Determination Checklist 16
MA-AA-203-1001 Work Order Planning 27
OP-AA-108-1000 OPERATOR CHALLENGES PROGRAM 8
MANAGEMENT
OPS-529 OPERATIONS DEFICIENCY AND 17
TAGGING POLICY
PI-AA-100-1005 Root Cause Analysis 26
PI-AA-100-1005-F03 Nuclear Safety Culture Evaluation Form
PI-AA-1003 Sharing Operating Experience with Nuclear 15
Industry
PI-AA-102 Operating Experience Program 20
PI-AA-102-1000 Significant Operating Experience Report 21
(SOER) and INPO Event Report (IER)
Process Implementation
PI-AA-102-1001 Operating Experience Program Screening 28
and Responding to Incoming Operating
Experience
Pl-AA-100-1007 Issue Investigation 28
PSL-BFJR-13-001 Risk Significance Determination of SSCs for 3
St. Lucie Units 1 & 2
Self- PSL 19-009 St. Lucie Nuclear Assurance Report - 2/6/2020
Assessments Performance Improvement
PSL 20-005 St. Lucie Nuclear Assurance Report - 8/6/2020
Operations
PSL 20-006 St. Lucie Nuclear Assurance Report - 7/9/2020
Maintenance and Work Management
Inspection Type Designation Description or Title Revision or
Procedure Date
PSL 21-003 St. Lucie Nuclear Assurance Report - 04/28/2021
Access Authorization/Fitness for Duty
PSL 21-004 St. Lucie Nuclear Assurance Report - QA 5/20/2021
Programs and Records Management
PSL 21-005 St. Lucie Nuclear Assurance Report - 06/30/2021
Engineering
PSL 21-009 St. Lucie Nuclear Assurance Report - 12/15/2021
Training
PSL 21-010 St. Lucie Nuclear Assurance Report - 2/4/2022
Performance Improvement
PSL 22-003 St. Lucie Nuclear Assurance Report - 4/8/2022
Radiation Protection
Work Orders 40822051 40822561 40692228
40823167 40824133 40723987
40627600 40353539 40704676
40601214 40641402 40704677
40731950 40785620 40712479
40713819 94218741 40792125
11