IR 05000335/2022011

Triennial Fire Protection Inspection Report 05000335/2022011 and 05000389/2022011

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, Signed by McCoy, Gerald on 12/27/22 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: DPR-67 and NPF-16 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 Enclosure

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.

(1) EC 294966, Unit 1 ECCS Pump Room Incipient Fire Detection System Replacement

(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 Type Designation Description or Title Revision or

Procedure Date

71111.21N.05 Calculations PSL-1FJF-98-024 Retran Analysis of PSL1 Appendix R Scenarios (CRI/Non Rev. 0

CRI Cases)

Corrective Action AR 02281179 Potential concern that incorrect Cat ID fuses SWS0LQV 09/22/2018

Documents 09/19/2018 were used for 2A3 & 2B3 4160V Switchgear trip

& close fuse SWS0LQV 09/19/2018 replacements

AR 02441855 During a review of post fire recovery actions, it was 11/15/2022

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.

CR 2320738 2019 NRC TFPI: The Testing and Inspection of Fire 07/11/2019

Dampers

Corrective Action AR 2442728 2022 FPTI: Smoldering Cigarette Found in 1 TGB 11/30/2022

Documents AR 2442772 2022 FPTI: ADM-19, Fire Protection Plan Contains Legacy 11/30/2022

Resulting from Guidance

Inspection AR 2442814 2022 FPTI: Inspection Team Questions Securing of Delay 12/01/2022

Gate

AR 2443111 2022 FPTI: U1 -0.50 Aerosol Smoke Check Canisters 12/05/2022

Found Unattended

AR 2443648 2022 FPTI: TC Adjacent to Energized Electrical Equipment 12/12/2022

AR 2443791 2022 FPTI: U1 ECCS IFD PMCR Incomplete 12/13/2022

AR 2443874 2022 FPTI: U1 RAB 19.5 1B Elec Pen Room Transient 12/14/2022

Combustible

PCR 2442771 ADM-19 - Fire Protection Plan 11/30/2022

Drawings 2998-B-327, Control Wiring Diagram for Relieve Valve V-1474 Rev. 11

Sheet 1629

2998-B-327, Control Wiring Diagram for SAS Isolation CAB Rev. 2

Sheet 1763 Interconnection

2998-B-327, Control Wiring Diagram for SAS Isolation CAB. Rev. 1

Sheet 1766 Interconnection

2998-B-327, Control Wiring Diagram for AUX FWP 2A Discharge to STM Rev. 17

Sheet 610 GEN 2B MV-09-13

Inspection Type Designation Description or Title Revision or

Procedure Date

2998-G-079, Flow Diagram Main Steam System Rev. 46

Sheet 1

2998-G-080, Flow Diagram Feedwater and Condensate System Rev. 39

Sheet 28

2998-G-080, Flow Diagram Feedwater and Condensate Systems Rev. 47

Sheet 2A

8770-B-327 Control Wiring Diagram for Relieve Valves V-1402 and V- Rev. 21

1404

PCI FD-1 Type 1 Fire Damper Sleeve Details Rev. 3

Engineering 294227 REVISE PSL-FPER-11-002 TO CHANGE THE ACTIONS 06/15/2020

Changes FOR MV-08-19A

294966 Unit 1 ECCS Pump Room Incipient Fire Detection System Rev. 0

Replacement

Engineering St. Lucie Unit 2 Updated Final Safety Analysis Report

Evaluations 0027-0009-003- Expert Panel for Addressing Multiple Spurious Operations Rev. 1

001

DBD-FP-1 Fire Protection Design Basis Document Rev. 07

PSL-ARCPLUS- St. Lucie Nuclear Safety Capability Assessment Rev. 0

001

PSL-BFJR-16- St. Lucie NFPA 805 - Tasks 1 & 6 Plant Partitioning and Rev. 03

040 Ignition Frequencies

PSL-BFJR-16- St. Lucie NFPA 805 - Human Failure Evaluation Report Rev. 02

041

PSL-BFJR-16- St. Lucie NFPA 805 - Scenario Development Rev. 03

2

PSL-BFJR-16- St. Lucie NFPA 805 - Summary Report Rev. 05

043

PSL-BFJR-16- St. Lucie NFPA 805 - Evaluation of the Unit 2 Control Room Rev. 0

047 Abandonment Times at the St. Lucie Nuclear Power Plant

PSL-FPER-11- St Lucie Nuclear Power Plant Units 1 and 2 NFPA 805 Rev. 03

2 Recovery Action Feasibility Evaluation

Fire Plans 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

PFP-2-ST Pre-Fire Plan U2 Steam Trestle/Aux Feed Water Pumps Rev. 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous 8770-14298 ECCS Pump Room Incipient Fire Detection System Vendor Rev. 02

Manual

Operability 2-ADM-09.23 Time Critical Operator Actions and Time Sensitive Operator Rev. 22

Evaluations Actions Program

Procedures 1-AOP-01.10 Pressurizer Pressure and Level Rev. 19

1-AOP-100.02 Control Room Inaccessibility Rev. 08

1-FME-15.02 12 Month Operability Test of the Fire Protection Sprinkler Rev. 7

System for the Unit 1 RAB

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 Auxiliary Feedwater 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 18 Month Operability Test of the Fire Protection Sprinkler Rev. 8

System for the Unit 2 RAB

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

MA-AA-100-1008 STATION HOUSEKEEPING AND MATERIAL CONTROL Rev. 30

MA-AA-203-1000 Maintenance Testing Rev. 19

PSL-ENG-LRAM- FIRE PROTECTION PROGRAM LICENSE RENEWAL Rev. 11

00-094 BASIS DOCUMENT

PSL-ENG-SEMS- Nuclear Safety Capability Assessment Basis Document-Unit Rev. 7

98-067 2

Work Orders 40628055 Remote Shutdown Panel 18 Month Functional Test 02/17/2020

4071073901 Remote Shutdown Components 18 Month Functional Test 10/04/2021

WO 40592245-01 FP LCL CNTL PNL 1F:12M SPRINKLER TEST 07/06/2019

WO 40671831-01 U2: RAB SPRINKLER SYSTEM TEST 06/19/2020

WO 40695623-01 FP LCL CNTL PNL 1F:12M SPRINKLER TEST 08/13/2020

WO 40757982-01 FP LCL CNTL PNL 1F:12M SPRINKLER TEST 11/09/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

WO 40764946-01 U2: RAB SPRINKLER SYSTEM TEST 04/22/2022

WO 4083374401 U1 IFD ECCS PP RM, Vesda Det ZN-2D - In Alarm 12/14/2022

WO 4083374601 U1 DGP D, ECCS Pump Room IFD Zone 1D - In Alarm 12/14/2022

Status

8