IR 05000335/2019011
| 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
August 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:
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
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
- (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
Procedure
Type
Designation
Description or Title
Revision or
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
Action
Documents
00552283,
00581639,
2311916,
97-2521-1,
97-2529-2
71111.05XT Corrective
Action
Documents
Resulting from
Inspection
2318513,
2318397,
2318541,
2318656,
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
Procedure
Type
Designation
Description or Title
Revision or
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
Evaluations
27-0009-003-001
MSO expert panel report
Rev. 001
27071-RPT-01
PSL Fire Risk Evaluation Expert Panel
PSL-2FSE-08-
001_001
Breaker Coordination Evaluation
Rev. 01
PSL-BFJR-16-044
St. Lucie NFPA 805 - Hot Gas Layer and Multi-
Compartment Analysis
Rev. 2
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.
Lucie Unit 1
Fire Pre-Plan West Main Hallway
Rev. 1
PFP-1-RAB 43' St.
Lucie Unit 1
Fire Pre-Plan Cable Spreading Room, Static Inverter
Room, RAB West Stairwell
Rev. 1
PFP-2-RAB 43' St.
Lucie Unit 2
Fire Pre-Plan B Switchgear Room, A DC Equipment
Room
Rev. 1
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
71111.05XT
Procedures
1-ADM-09.23
Time Critical Operator Actions and Time Sensitive
Actions Program
1-AOP-100.01
Response to Fire
1-AOP-100.02
Control Room Inaccessibility
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
Procedure
Type
Designation
Description or Title
Revision or
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
Fire Protection Screening
Rev. 9
Maintenance Testing
Rev. 10
PSL-ENG-SEMS-98-
035
Nuclear Safety Capability Assessment Basis Document
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