IR 05000335/2019011

Triennial Fire Protection Inspection Report 05000335/2019011 and 05000389/2019011

ML19232A176
Person / Time
Site:	Saint Lucie
Issue date:	08/20/2019
From:	Scott Shaeffer Division of Reactor Safety II
To:	Moul D Florida Power & Light Co
References
IR 2019011
Download: ML19232A176 (9)

Text

ust 20, 2019

SUBJECT:

SAINT LUCIE UNITS 1 AND 2 - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000335/2019011 AND 05000389/2019011

Dear Mr. Moul:

On July 11, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Saint Lucie Units 1 and 2 and discussed the results of this inspection with Mr. Boyd Beltz and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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/

Scott M. Shaeffer, Chief Engineering Branch 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: 05000335/2019011 and 05000389/2019011 Enterprise Identifier: I-2019-011-0038 Licensee: Florida Power & Light Facility: Saint Lucie, Units 1 and 2 Location: Jensen Beach, FL 34957 Inspection Dates: June 17, 2019 to July 12, 2019 Inspectors: P. Braaten, Reactor Inspector J. Dymek, Reactor Inspector L. Jones, Senior Reactor Inspector M. Singletary, Reactor Inspector Approved By: Scott M. Shaeffer, Chief Engineering Branch 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 Saint Lucie 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.

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

71111.05XT - Fire Protection - NFPA 805 B.5.b Inspection Activities (IP Section 02.03)

The inspectors evaluated the following B.5.b Mitigating Strategies:

(1) Manually Depressurize Steam Generators and Makeup with Portable Pump Fire Protection Inspection Requirements (IP Section 02.01a) (4 Samples)

The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:

(1) Fire Area 1B - Unit 1 Cable Spreading Room Analyzed Circuits:

• Switchgear 1B3

• 1-AFW PP-1B

(2) Fire Area 1O - Unit 1 RAB Hallway, -0.05' Elevation Analyzed Circuits:

• Train A Pressurizer PORV

(3) Fire Area 2C - Unit 2 "B" Switchgear Room Analyzed Circuits:

• MV 08-13, 2A S/G to 2C AFW

• MV 14-13, CCW to Containment Cooler

• MV 14-14. CCW to Containment Cooler

• MV 09-10/ SE 09-3, AFW Pump Discharge to 2B S/G

(4) Fire Area 2D - Unit 2 "A" DC Equipment Room

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On July 11, 2019, the inspectors presented the triennial fire protection inspection results to Mr. Boyd Beltz and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05XT Calculations DBD-FP-1 Fire Protection System NFPA 805 Design Basis Rev. 5

PSL-ARCPLUS-001 Nuclear Safety Capabilities Assessment Rev. 1

PSL-BFJR-16-043 St. Lucie NFPA 805 - Summary Report Rev. 4

71111.05XT Corrective 00552283,

Action 00581639,

Documents 02311916,

97-2521-1,

97-2529-2

71111.05XT Corrective 2318513,

Action 2318397,

Documents 2318541,

Resulting from 2318656,

Inspection 2318742,

20738,

20739

71111.05XT Drawings 2998-B-327 Auxiliary Feedwater Pump 2A Rev. 26

2998-B-327 Charging Pump 2A Rev. 26

2998-B-327 Pressurizer Pressure and Level Rev. 14

2998-G-275_Sh16 U2 One-Line 6.9KV Busses 2A1 & 2B1 Rev. 14

2998-G-275_Sh2 U2 One-Line 125VDC Bus 2B & 2BB Rev. 9

2998-G-275_Sh31 U2 One-Line 480V MCC 2A5 Rev. 16

8770-B-054 Fire Protection Penetration Schedule

8770-B-327 Sh. 178 Charging Pump 1B Rev. 27

8770-B-327 Sh. 630 Auxiliary Feedwater Pump 1B Rev. 30

8770-B-327 Sheet 138 Pressurizer Level Ch. L-1110-1 Rev. 27

8770-B-327, Sh 98 Pressurizer Pressure CH. P-1100Y Rev. 16

8770-G-165 Reactor Auxiliary Building Fire Dampers, Fire Doors,

and Halon Suppression Areas, El. 43'-0"

8770-G-274 U1 One-Line 480V Swgr & MCCs R025

8770-G-274 Auxiliary One Line Diagram Rev. 25

8770-G-594 Composite Penetrations Interior Fire Walls, El. 0.50'

8770-G-784 Doors and Windows Schedule

Inspection Type Designation Description or Title Revision or

Procedure Date

8770-G-820 Safety/Non-Safety Related Block Walls, Reactor

Auxiliary Building, El. -0.50'

8770-G-881 HVAC Equipment Schedule and Details

71111.05XT Engineering 0027-0009-003-001 MSO expert panel report Rev. 001

Evaluations

27071-RPT-01 PSL Fire Risk Evaluation Expert Panel 1

PSL-2FSE-08- Breaker Coordination Evaluation Rev. 01

001_001

PSL-BFJR-16-044 St. Lucie NFPA 805 - Hot Gas Layer and Multi- Rev. 2

Compartment Analysis

PSL-FPER-09-037 NFPA Code 90A-1978 Conformance Review

PSL-FPER-09-046 NFPA 805 Non-Power Operations Review Rev. 2

PSL-FPER-11-002 NFPA 805 Recovery Action Feasibility Evaluation Rev. 2

PSL-FPER-11-010 NFPA 805 Fire Area Transition Review Rev. 1

71111.05XT Fire Plans PFP-1-RAB -0.50' St. Fire Pre-Plan West Main Hallway Rev. 1

Lucie Unit 1

PFP-1-RAB 43' St. Fire Pre-Plan Cable Spreading Room, Static Inverter Rev. 1

Lucie Unit 1 Room, RAB West Stairwell

PFP-2-RAB 43' St. Fire Pre-Plan B Switchgear Room, A DC Equipment Rev. 1

Lucie Unit 2 Room

71111.05XT Miscellaneous Plant Fire Protection Program Impairment Log 06/17/2019

Plant Fire Protection Program Impairment Log 06/19/2019

0033007-RPT-002 NFPA Monitoring Program Scoping Report Rev. 1

2998-18487 Installation and Maintenance Manual for Pullman Fire Rev. 1

Dampers

71111.05XT Procedures 1-ADM-09.23 Time Critical Operator Actions and Time Sensitive 16

Actions Program

1-AOP-100.01 Response to Fire 6

1-AOP-100.02 Control Room Inaccessibility 1

1-FMM-99.07 Fire House and Equipment Inventory Rev. 5

2-FMM-99.11 Unit 2 Fire Damper Inspection Rev. 3

2-FMM-99.11 Unit 2 Fire Damper Inspection Rev. 4

2-FMM-99.12 Unit 2 Fire Door Inspection Rev. 6

Inspection Type Designation Description or Title Revision or

Procedure Date

2-OSP-15.11 Unit 2 Fire Door Surveillance Rev. 12

71111.05XT Procedures ADM-11.01 Standardized Terminology Rev. 35

ADM-19.00 Fire Protection Plan Rev. 9

ADM-19.03 Transient Combustible Control Rev. 8

ADM-19.04 Implementation of the NFPA 805 Monitoring Program Rev. 2

EN-AA-202-1004 Fire Protection Screening Rev. 9

MA-AA-203-1000 Maintenance Testing Rev. 10

PSL-ENG-SEMS-98- Nuclear Safety Capability Assessment Basis Document 7

035

71111.05XT Work Orders 40477425-01 Unit 2, FDPR-25-19 Has Broken Springs 11/16/2017

40489651-01 Unit 2, FDPR-25-109 Has Broken Springs 10/04/2018

40523893-01 Fire Damper Inspections 06/08/2018

40578241-61 DSC Welding Hot Work Permit 06/17/2019

40604312-01 Unit 2, FDPR-25-129 Has Broken Springs 11/28/2018

40620357-01 Fire Pump 1B Monthly Operability Test 06/19/2019

40632812-01 Unit 1, FDPR-25-117 Has Broken Spring 11/17/2018

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