IR 05000335/2022011
| ML22357A008 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/27/2022 |
| From: | Gerald Mccoy Division of Reactor Safety II |
| To: | Coffey B Florida Power & Light Co |
| References | |
| IR 2022011 | |
| Download: ML22357A008 (10) | |
Text
December 27, 2022
SUBJECT:
ST. LUCIE - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000335/2022011 AND 05000389/2022011
Dear Bob Coffey:
On December 15, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at St. Lucie and discussed the results of this inspection with Mr. Robert Craven and other members of your staff. The results of this inspection are documented in the enclosed report.
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, Gerald J. McCoy, Chief Engineering Br 2 Division of Reactor Safety Docket Nos. 05000335 and 05000389 License Nos. DPR-67 and NPF-16
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000335 and 05000389
License Numbers:
Report Numbers:
05000335/2022011 and 05000389/2022011
Enterprise Identifier:
I-2022-011-0019
Licensee:
Florida Power & Light Company
Facility:
St. Lucie
Location:
Jensen Beach, FL
Inspection Dates:
November 28, 2022 to December 15, 2022
Inspectors:
P. Braaten, Senior Reactor Inspector
W. Monk, Senior Reactor Inspector
J. Montgomery, Senior Reactor Inspector
D. Strickland, Reactor Inspector
Approved By:
Gerald J. McCoy, Chief
Engineering Br 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at St. Lucie, 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.
REACTOR SAFETY
71111.21N.05 - Fire Protection Team Inspection (FPTI) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)
The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).
- (1) Unit 2 Auxiliary Feedwater System
- (2) Unit 2 4160V Electrical Distribution System
- (3) Preaction Sprinkler System in Unit 2 FA I/FZ 2-23 (2B Electrical Penetration Room)
- (4) Preaction sprinkler system in Unit 1 FA C/FZ 1-55W (Main Hallway West, Cable Loft Area)
Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)
The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.
- (1) Combustible Control Program
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors verified the following:
a. Changes to the approved FPP do not constitute an adverse effect on the ability to safely shutdown.
b. The adequacy of the design modification, if applicable.
c. Assumptions and performance capability stated in the SSA have not been degraded through changes or modifications.
d. The FPP documents, such as the Updated Final Safety Analysis Report, fire protection report, FHA, and SSA were updated consistent with the FPP or design change.
e. Post-fire SSD operating procedures, such as abnormal operating procedures, affected by the modification were updated.
- (2) EC 294227, Revise PSL-FPER-11-002 To Change the Actions For MV-08-19A (Atmospheric Dump Valve for SG 2A)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On December 15, 2022, the inspectors presented the triennial fire protection inspection results to Mr. Robert Craven and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
PSL-1FJF-98-024
Retran Analysis of PSL1 Appendix R Scenarios (CRI/Non
CRI Cases)
Rev. 0
Potential concern that incorrect Cat ID fuses SWS0LQV
09/19/2018 were used for 2A3 & 2B3 4160V Switchgear trip
& close fuse SWS0LQV 09/19/2018 replacements
09/22/2018
During a review of post fire recovery actions, it was
discovered that there are several [inconsistencies] between
the fire protection DBD (DBD-FP-1) and the Nuclear Safety
Capability Assessment (NSCA) with respect to recovery
actions.
11/15/2022
Corrective Action
Documents
CR 2320738
2019 NRC TFPI: The Testing and Inspection of Fire
07/11/2019
22 FPTI: Smoldering Cigarette Found in 1 TGB
11/30/2022
22 FPTI: ADM-19, Fire Protection Plan Contains Legacy
Guidance
11/30/2022
22 FPTI: Inspection Team Questions Securing of Delay
Gate
2/01/2022
22 FPTI: U1 -0.50 Aerosol Smoke Check Canisters
Found Unattended
2/05/2022
22 FPTI: TC Adjacent to Energized Electrical Equipment
2/12/2022
22 FPTI: U1 ECCS IFD PMCR Incomplete
2/13/2022
22 FPTI: U1 RAB 19.5 1B Elec Pen Room Transient
Combustible
2/14/2022
Corrective Action
Documents
Resulting from
Inspection
PCR 2442771
ADM-19 - Fire Protection Plan
11/30/2022
2998-B-327,
Sheet 1629
Control Wiring Diagram for Relieve Valve V-1474
Rev. 11
2998-B-327,
Sheet 1763
Control Wiring Diagram for SAS Isolation CAB
Interconnection
Rev. 2
2998-B-327,
Sheet 1766
Control Wiring Diagram for SAS Isolation CAB.
Interconnection
Rev. 1
71111.21N.05
Drawings
2998-B-327,
Sheet 610
Control Wiring Diagram for AUX FWP 2A Discharge to STM
GEN 2B MV-09-13
Rev. 17
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2998-G-079,
Sheet 1
Flow Diagram Main Steam System
Rev. 46
2998-G-080,
Sheet 28
Flow Diagram Feedwater and Condensate System
Rev. 39
2998-G-080,
Sheet 2A
Flow Diagram Feedwater and Condensate Systems
Rev. 47
8770-B-327
Control Wiring Diagram for Relieve Valves V-1402 and V-
1404
Rev. 21
PCI FD-1
Type 1 Fire Damper Sleeve Details
Rev. 3
294227
REVISE PSL-FPER-11-002 TO CHANGE THE ACTIONS
FOR MV-08-19A
06/15/2020
Engineering
Changes
294966
Unit 1 ECCS Pump Room Incipient Fire Detection System
Replacement
Rev. 0
St. Lucie Unit 2 Updated Final Safety Analysis Report
27-0009-003-
001
Expert Panel for Addressing Multiple Spurious Operations
Rev. 1
DBD-FP-1
Fire Protection Design Basis Document
Rev. 07
PSL-ARCPLUS-
001
St. Lucie Nuclear Safety Capability Assessment
Rev. 0
PSL-BFJR-16-
040
St. Lucie NFPA 805 - Tasks 1 & 6 Plant Partitioning and
Ignition Frequencies
Rev. 03
PSL-BFJR-16-
041
St. Lucie NFPA 805 - Human Failure Evaluation Report
Rev. 02
PSL-BFJR-16-
2
St. Lucie NFPA 805 - Scenario Development
Rev. 03
PSL-BFJR-16-
043
St. Lucie NFPA 805 - Summary Report
Rev. 05
PSL-BFJR-16-
047
St. Lucie NFPA 805 - Evaluation of the Unit 2 Control Room
Abandonment Times at the St. Lucie Nuclear Power Plant
Rev. 0
Engineering
Evaluations
PSL-FPER-11-
2
St Lucie Nuclear Power Plant Units 1 and 2 NFPA 805
Recovery Action Feasibility Evaluation
Rev. 03
PFP-1-RAB-19.5
UNIT 1 REACTOR AUXILIARY BUILDING
Rev. 2
PFP-1RAB-(-0.5)
Pre-Fire Plan U1 Reactor Auxiliary Building
Rev. 2
Fire Plans
Pre-Fire Plan U2 Steam Trestle/Aux Feed Water Pumps
Rev. 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
8770-14298
ECCS Pump Room Incipient Fire Detection System Vendor
Manual
Rev. 02
Operability
Evaluations
2-ADM-09.23
Time Critical Operator Actions and Time Sensitive Operator
Actions Program
Rev. 22
1-AOP-01.10
Pressurizer Pressure and Level
Rev. 19
1-AOP-100.02
Control Room Inaccessibility
Rev. 08
1-FME-15.02
Month Operability Test of the Fire Protection Sprinkler
System for the Unit 1 RAB
Rev. 7
1-FMM-99.11
FIRE DAMPER INSPECTION
Rev. 2
1-PMI-15.04
Unit 1 Incipient Fire Detector Testing and Maintenance
Rev. 08
2-AOP-01.10
Pressurizer Pressure and Level
Rev. 18
2-AOP-09.02
Rev. 19
2-AOP-100-12
Response to Fire - Fire Areas
Rev. 12
2-AOP-100.01
Response to Fire
Rev. 12
2-AOP-100.02
Control Room Inaccessibility
Rev. 11
2-AOP-100.11
Response to Fire - Fire Zones
Rev. 18
2-FME-15.02
Month Operability Test of the Fire Protection Sprinkler
System for the Unit 2 RAB
Rev. 8
ADM-19.00
FIRE PROTECTION PLAN
Rev. 24
ADM-19.03
Transient Combustible Control
Rev. 17
ADM-19.07
CONTROL OF IGNITION SOURCES AND HOT WORK
Rev. 8
STATION HOUSEKEEPING AND MATERIAL CONTROL
Rev. 30
Maintenance Testing
Rev. 19
PSL-ENG-LRAM-
00-094
FIRE PROTECTION PROGRAM LICENSE RENEWAL
BASIS DOCUMENT
Rev. 11
Procedures
PSL-ENG-SEMS-
98-067
Nuclear Safety Capability Assessment Basis Document-Unit
Rev. 7
40628055
Remote Shutdown Panel 18 Month Functional Test
2/17/2020
4071073901
Remote Shutdown Components 18 Month Functional Test
10/04/2021
FP LCL CNTL PNL 1F:12M SPRINKLER TEST
07/06/2019
WO 40671831-01 U2: RAB SPRINKLER SYSTEM TEST
06/19/2020
FP LCL CNTL PNL 1F:12M SPRINKLER TEST
08/13/2020
Work Orders
FP LCL CNTL PNL 1F:12M SPRINKLER TEST
11/09/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
U2: RAB SPRINKLER SYSTEM TEST
04/22/2022
U1 IFD ECCS PP RM, Vesda Det ZN-2D - In Alarm
2/14/2022
U1 DGP D, ECCS Pump Room IFD Zone 1D - In Alarm
Status
2/14/2022