IR 05000250/2021012
| ML21125A227 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 05/05/2021 |
| From: | David Dumbacher NRC/RGN-II/DRP/RPB3 |
| To: | Moul D Florida Power & Light Co |
| References | |
| IR 2021012 | |
| Download: ML21125A227 (20) | |
Text
May 5, 2021
SUBJECT:
TURKEY POINT UNITS 3 & 4 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000250/2021012 AND 05000251/2021012
Dear Mr. Moul:
On March 26, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Turkey Point Units 3 & 4 and discussed the results of this inspection with Mr. Michael Pearce and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action 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 corrective action 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,
/RA/
David E. Dumbacher, Acting Chief Reactor Projects Branch 3 Division of Reactor Projects
Docket Nos. 05000250 and 05000251 License Nos. DPR-31 and DPR-41
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000250 and 05000251
License Numbers:
Report Numbers:
05000250/2021012 and 05000251/2021012
Enterprise Identifier: I-2021-012-0003
Licensee:
Florida Power & Light Company
Facility:
Turkey Point Units 3 & 4
Location:
Homestead, FL 33035
Inspection Dates:
March 08, 2021 to March 26, 2021
Inspectors:
A. Beasten PhD, Resident Inspector
A. Goldau, Operations Engineer
N. Pitoniak, Sr. Fuel Facility Project Inspector
R. Reyes, Resident Inspector
Approved By:
David E. Dumbacher, Chief
Reactor Projects Branch 3
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Turkey Point Units 3 & 4, 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 02.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of the high head safety injection system and instrument air systems.
- Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, 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 Corrective Action Program Assessment: Based on the samples reviewed, the team determined that the licensees corrective action program (CAP) complied with regulatory requirements and self-imposed standards. The licensees implementation of the CAP adequately supported nuclear safety.
Effectiveness of Problem Identification: The inspectors determined that the licensee was effective in identifying problems and entering them into the CAP at the appropriate threshold. This conclusion was based on a review of the requirements for initiating action requests (ARs) as described in licensee procedure PI-AA-104-1000, "Condition Reporting,"
and the site's management expectation that employees were encouraged to initiate condition reports. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues. The inspectors reviewed ARs system health trending for Component Cooling Water Systems, High Head Safety Injection, Emergency Diesel Generators, and the Instrument Air System, and performed walkdowns of accessible portions of select systems. Based on the inspectors' reviews and walk downs, the inspectors determined that deficiencies were being identified and placed in the CAP.
Effectiveness of Problem Prioritization and Evaluation: Based on the review of ARs sampled by the inspection team during the onsite period, the inspectors concluded that problems were generally prioritized and evaluated in accordance with the AR significance determination guidance in procedure PI-AA-104-1000. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that plant personnel had generally conducted cause evaluations in compliance with the licensees CAP procedures, including appropriate cause determinations, and performed adequate levels of analysis based on the significance of the issues being evaluated.
Effectiveness of Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that corrective actions were effective, timely, and commensurate with the safety significance of the issues. For significant conditions adverse to quality, the corrective actions directly addressed the cause and effectively prevented recurrence. The inspectors reviewed performance indicators, CRs, and effectiveness reviews, as applicable, to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to preclude repetition (CAPRs) were sufficient to ensure corrective actions were properly implemented and were effective.
Assessment 71152B Operating Experience, Self-Assessments, and Audits: The inspectors examined the licensee's program for obtaining and using industry operating experience. This included a review of procedure PI-AA-102, "Operating Experience Program," selected corrective action program action requests, and the licensees operating experience (OE) database to assess the effectiveness of how external and internal OE data was evaluated at the plant. Additionally, the inspectors selected OE documents such as NRC generic communications, licensee event reports, vendor notifications, and plant internal OE items which had been issued since March 2019 to verify that the licensee had appropriately evaluated each notification for applicability to the station, and whether issues identified through these reviews were entered into the CAP.
The inspectors determined that the scopes of assessments and audits were adequate. Self-assessments were generally detailed and critical. The inspectors verified that ARs were created to document areas for improvement and findings resulting from self-assessments and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.
The inspectors determined that the station's processes for the use of industry and NRC operating experience information and for the performance of audits and self-assessments were effective and complied with all regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The inspectors concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented to address lessons learned as needed. The inspectors determined that the licensee was effective at performing self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance.
Assessment 71152B Safety Conscious Work Environment: Based on a sample of at least 20 individuals interviewed from a cross-section of plant employees, the inspectors found no evidence of challenges to the safety conscious work environment. Employees interviewed appeared knowledgeable of avenues to raise safety concerns and appeared willing to raise nuclear safety concerns through at least one of the several means available.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 26, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Michael Pearce and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
AR 2200628
AR 2213896
AR 2237081
AR 2264848
AR 2272412
AR 2272889
AR 2276438
AR 2280053
AR 2280735
AR 2281268
AR 2282120
AR 2284896
AR 2289523
AR 2291542
AR 2292350
AR 2295754
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2296056
AR 2298655
AR 2299807
AR 2301281
AR 2303820
AR 2304807
AR 2305193
AR 2305543
AR 2306492
AR 2307666
AR 2307809
AR 2307812
AR 2308244
AR 2310652
AR 2312024
AR 2312394
AR 2312778
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2313135
AR 2315197
AR 2316085
AR 2316933
AR 2317068
AR 2319017
AR 2319909
AR 2320784
AR 2321909
AR 2323721
AR 2324645
AR 2326181
AR 2327236
AR 2327837
AR 2328386
AR 2329403
AR 2330086
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2331221
AR 2331477
AR 2331776
AR 2333615
AR 2334407
AR 2335236
AR 2336036
AR 2336802
AR 2341929
AR 2342702
AR 2343970
AR 2344584
AR 2344617
AR 2344656
AR 2344692
AR 2345574
AR 2347144
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2347886
AR 2349189
AR 2352363
AR 2354585
AR 2354721
AR 2354725
AR 2354737
AR 2355529
AR 2355849
AR 2356436
AR 2356439
AR 2356982
AR 2359498
AR 2361794
AR 2364676
AR 2365425
AR 2365708
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2365716
AR 2365722
AR 2365970
AR 2366093
AR 2367875
AR 2368902
AR 2370137
AR 2371379
AR 2373717
AR 2379516
AR 2379864
AR 2379866
AR 2379869
AR 2380481
AR 2380655
AR 2383376
AR 2385185
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
AR 2387275
Drawings
5613-M-3047
Chemical and Volume Control System
Miscellaneous
5610-019-DB-002
PTN Unit 3 and 4 Intake Cooling Water System Design
Requirements
Miscellaneous
LER 2020-001-00
Technical Specification Action Not Taken for Unrecognized
Inoperable Reactor Protection System (RPS) and
Engineered Safety Feature Actuation System (ESFAS)
Instrument Channel.
6/24/2020
Miscellaneous
LER 2020-002-00
Manual Reactor Trip in Response to High Steam Generator
Level following Inadvertent Opening of Feedwater Heater
Bypass Valve
9/23/2020
Miscellaneous
LER 2020-003-00
Automatic Reactor Trip due to High Source Range Flux
during Reactor Startup
9/29/2020
Miscellaneous
LER 2020-004-00
Manual Reactor Trip from 34% Power in Response to
Automatic Trip of the 3B Steam Generator Feedwater Pump
Miscellaneous
LER 2020-005-00
POR determined N-3-32 inoperable since 4/1/2020 (PT3-31
shutdown)
Miscellaneous
PTN Unit 3 and 4
Equipment
Qualification
Documentation
Package 1001
Treatment of Issues
Miscellaneous
PTN Unit 3 and 4
Equipment
Qualification
Documentation
Package 14.1
Nutherm Starters
Procedures
0-ADM-016
Procedures
0-ADM-032
NRC Performance Indicators Turkey Point
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0-ADM-051
Outage Risk Assessment and Control
Procedures
0-ADM-211
Emergency And Off-Normal Operating Procedure Usage
Procedures
0-ADM-225
On Line Risk Assessment and Management
Procedures
0-ADM-511
Post Trip Review (PTR)
Procedures
0-ADM-561
Structures Monitoring Program
Procedures
3-EOP-FR-H.1
Response To Loss Of Secondary Heat Sink
Procedures
3-GOP-100
Fast Load Reduction
Procedures
3-GOP-103
Power Operation to Hot Standby
Procedures
3-NOP-040.02
Refueling Core Shuffle
Procedures
3-NOP-040.03
Fuel Handling And Insert Shuffle In The Spent Fuel Pit
Procedures
3-NOP-075
Auxiliary Feedwater System Malfunction
Procedures
3-OSP-023.1
Diesel Generator Operability Test
Procedures
3-OSP-047.2
3-312A, 3-312B, and 3-312C Inservice Test
Procedures
3-OSP-206.2
Quarterly Inservice Valve Testing
Procedures
3-PMI-059.36
PRNI Protection set II channel N-42 Installation of new
current and streaming constant at shutdown
Procedures
4-ONOP-004.2
Loss of 4A 4KV Bus
Procedures
4-ONOP-067
Radioactive Effluent Release
Procedures
Preparation, Revision, Review / Approval of Procedures
Procedures
Procedures
BO-AA-103-1001-
10003
Long Term Asset Management Entries
Procedures
Nuclear Fleet Long Range Planning
Procedures
Operability Determinations/Functionality Assessments
Procedures
Nuclear Division Pandemic Influenza Procedure
Procedures
Maintenance Rule Program Administration
Procedures
Equipment Reliability
Procedures
Inservice Testing (IST) Program
Procedures
ER-AA-113-1001-
10000
Evaluation Guidelines for Relief Valve Failures
Procedures
System and Program Health Reporting
Procedures
System Performance Monitoring
Procedures
EVT-050-2020-
Maintenance Rule Functional Failure Assessment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
39591
Procedures
Conduct of Maintenance
Procedures
Scaffold Installation, Modification, Fleet Scaffold
Procedures
Preventative Maintenance and Surveillance Procedure
Procedures
MTG-PTN-2020-
263
Maintenance Rule Meeting Minutes
Procedures
Conduct of Operations
Procedures
Level 2 Independent Assessment Planning, Conduct, and
Reporting
Procedures
Root Cause Analysis
Procedures
Common Cause Evaluation
Procedures
Issue Investigation
Procedures
Assessment and Improvement Programs
Procedures
Level 1 Core Business Assessments
Procedures
Operating Experience Program
Procedures
Operating Experience Program Screening and Responding
to Incoming Operating Experience
Procedures
Condition Reporting
Self-Assessments 2345097-01 HU
Investigation
SDTC Runback
HU Error
Human Performance Investigation checklist
rev 042929
Self-Assessments AR 2356982
Escalation
Closure Package
PTN Organizational Effectiveness Fleet Escalation Closure
Report
Self-Assessments CR 2356982
Organizational
Effectiveness
Investigation
Checklist
Fleet Level Escalation (OP - ER station overall performance)
05/18/20
Self-Assessments Effectiveness
Review
Effectiveness Review - PTN escalation of OPS human
performance
final
Self-Assessments L1A 2282508
Level 1 Core Business Assessment - Review of NRC NCV
with Cross Cutting Aspect P.1
6/23/18 -
6/25/18
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-Assessments L1A 2338196
Level 1 Core Business Assessment - 4Q2020 Trend Review
Operations
10/1/20 -
2/31/20
Self-Assessments L1A 2338196
Level 1 Core Business Assessment - 4Q20 Operations Trend 10/1/20 -
2/31/20
Self-Assessments L1A 2364676
Level 1 Core Business Assessment - PTN H.12 Cross-cutting
Aspect
undated
Self-Assessments L2A 02374396
Nuclear Safety Culture Assessment
05/18/20 -
05/30/20 and
10/27/20 -
11/3/20
Self-Assessments Operations
Improvement
GADR Gaps 1-2
status report
Operations Improvement GADR Gaps 1-2 status report
updated
3/12/21
Self-Assessments PI-AA-100-1005-
F04
Effectiveness Review of DLAs
Self-Assessments PTN-17-008
Nuclear
Assurance Report
Turkey Point Nuclear Assurance Report - Audit, Performance
Improvement
01/17/18
Self-Assessments PTN-19-002
Nuclear
Assurance Report
Turkey Point Nuclear Assurance Report - Audit, QA
Programs and Records Management
3/30/19
Self-Assessments PTN-20-005
Nuclear
Assurance Report
Turkey Point Nuclear Assurance Report - Audit, Operations
07/13/20
Work Orders
WO 40201076
WO 40583625
WO 40649312
WO 40656961
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
WO 40665245
WO 40683334
WO 40699342