IR 05000335/2021010
| ML21341A496 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  (DPR-067, NPF-016) |
| Issue date: | 12/07/2021 |
| From: | James Baptist NRC/RGN-II/DRS/EB1 |
| To: | Moul D Florida Power & Light Co |
| References | |
| IR 2021010 | |
| Download: ML21341A496 (14) | |
Text
December 7, 2021
SUBJECT:
ST. LUCIE PLANT UNITS 1 & 2 - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000335/2021010 AND 05000389/2021010
Dear Mr. Moul:
On November 4, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at St. Lucie Plant Units 1 & 2. On November 18, 2021, the NRC inspectors discussed the results of this inspection with Mr. Wyatt Godes 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,
/RA/
James B. Baptist, Chief Engineering Branch 1 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:
05000335/2021010 and 05000389/2021010
Enterprise Identifier: I-2021-010-0043
Licensee:
Florida Power & Light Company
Facility:
St. Lucie Plant Units 1 & 2
Location:
Jensen Beach, FL
Inspection Dates:
October 18, 2021 to November 05, 2021
Inspectors:
J. Braisted, Reactor Inspector
S. Bussey, Sr.. Reactor Technology Instructor
W. Deschaine, Senior Resident Inspector
C. Franklin, Reactor Inspector
E. Haywood, General Engineer Nran
J. Nadel, Senior Resident Inspector
G. Ottenberg, Senior Reactor Inspector
Approved By:
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at St. Lucie Plant Units 1 & 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
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (3 Samples)
- (1) Unit 1 Instrument Air Check Valves: 1-V18279, 1-V18283, 1-V18290, 1-V18291, 1-V18294, 1-V18295
- Design bases documents, system descriptions, and training documents
- Primary design calculations
- Normal, Abnormal, and Emergency Operating Procedures
- Surveillance Test Procedures and Recent Results
- Material Condition of Valves and Associated Equipment
- Vendor Instruction Manuals
- Corrective Action History and System Health Reports
- Condition reports associated with component
- Local Leak Rate Test Procedure and Recent Results
- (2) Unit 2 Component Cooling Water (CCW) Heat Exchanger 2B
- Design bases documents and system descriptions
- Primary design calculations
- Normal, Abnormal, and Emergency Operating Procedures
- Corrective and Preventative Work Order History
- Generic Letter 89-13 Historical Correspondence
- Surveillance Test Procedures and Heat Exchanger Cleaning/Inspection Results
- Material Condition of Heat Exchanger, Pumps, Valves, and Associated Equipment
- Vendor Instruction Manuals
- Corrective Action History and System Health Reports
- Condition reports associated with component
- Maintenance Rule Program Documents
- (3) 480 Volt Switchgear Bus 2B2
- Normal, Abnormal, and Emergency Operating Procedures
- Compliance with Updated Final Safety Analysis Report (UFSAR), Technical Specifications (TS) and TS Bases
- Material condition and configuration (e.g., visual inspection during a walkdown)
- Consistency between station documentation (e.g., procedures) and vendor specifications
- Environmental Conditions
- Work Maintenance and surveillance test reviews
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
- (1) Unit 1 Containment Vacuum Relief Isolation Valve, FCV-25-8
- Local Leak Rate Test Procedure and Recent Results
- Quarterly Valve Cycle Surveillance Test Procedure and Recent Results
- Component, Control Scheme, and System Drawings
- Calculations to Demonstrate Ability to Perform Design Basis Safety Function and Accumulator Sizing
- Environmental Qualification of Valve Components
- Vendor Instruction Manuals
- Preventive Maintenance Program Strategy and Basis Documents
- System Health Reports and Corrective Action Documents
- Emergency and Abnormal Operating procedures
Modification Review - Permanent Mods (IP Section 02.03) (5 Samples)
- (1) EC 290267, Unit 2 TCV-14-4A Valve Stem Clamp Installation/Removal
- (2) EC 289528, Unit 1: Installation of Air Filtration Devices Upstream of V18290
- (4) EC 286011, Unit 1 HCV-14-8B Replacement
Review of Operating Experience Issues (IP Section 02.06) (1 Sample)
- (1) NRC Information Notice 2018-03: Operating Experience Regarding Failure to Meet Technical Specifications Requirements for Changing Plant Conditions
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 18, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Wyatt Godes and other members of the licensee staff.
- On November 4, 2021, the inspectors presented the initial inspection results to Mr. D.
Sluszka and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
2109-C-01
AOV Calculation for Unit 1 FCV-25-7 and FCV-25-8
2109-C-011
AOV Program Unit 1 HCV-14-8A, 8B, 9, 10 Valve/Actuator
Capability
2109-C-019
AOV Program Unit 2 TCV-14-4A/B Valve/Actuator Capability
29154-M-0100
Impact of Extended Power Uprate on Normal Operations
Radiation Levels, Shielding Adequacy, and Normal
Operation Radiation Environments in EQ Zones
29154-M-0115
Containment Vacuum Analysis at EPU Conditions
CN-OA-08-39
St. Lucie Unit 2 EPU Containment LOCA Pressure and
Temperature Analysis
CN-OA-09-9
St. Lucie Unit 2 EPU CCW/ICW Temperature Response
Analysis
PSL-1 FJM-90-
Emergency Diesel Generator Fuel Oil Supply St. Lucie Unit
24
PSL-1FJI-11-001
St Lucie Unit 1 Containment Hi/Lo Pressure Alarm Setpoints
PSL-2-J-M-90-
Accumulator Sizing for Vacuum Relief Valves
0013
PSL-2FSC-02-
Evaluation of Stem Clamp Restraint for Valve No. TCV-14-
007
4A in Support of CR 02-0957
Corrective Action
Action Request
2347524, 2352035, 2354805, 2385508, 2396400
Documents
(AR)
Action Request
1998799, 2072717, 2122786, 22801103, 2354805, 2385508,
(AR)
2396400, 2347524, 2352035, 2354805
Action Request
239658, 02392199, 02405470, 02193464
(AR)
Condition Report
2-0957
(CR)
Corrective Action
20 DBAI-Typo Error For Equip. Number in U2 CCW DBD
10/18/2021
Documents
NRC 2021 DBAI Cable Tray Housekeeping
10/19/2021
Resulting from
NRC 2021 DBAI ID of Cable-Tray Penetration Seal Cracking
10/19/2021
Inspection
NRC 2021 DBAI 480V SWGR 2B2 Station Service
10/19/2021
Transformer Leak
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21 DBAI-Editorial Error in DBD-CMTMT-1 Section
7.8.1.2a
10/20/2021
21 DBAI-1B EG: Room Air Intake As Visual Corrosion
10/20/2021
21 DBAI-1B EDG: Generator Bearing Sight Glass Oil Drip
10/20/2021
21 DBAI-1B1 Diesel Engine: Crankcase Air/Oil Separator
10/20/2021
21 DBAI-Minor Housekeeping Issue (CCW Building)
10/21/2021
21 DBAI-U2 HCV-14-8B Air Regulator Surface
Degradation
10/21/2021
21 DBAI-Ladder Had Been Stored Improperly
10/21/2021
21 DBAI-Grating Platform I-Beam Degraded (U2 Intk
Struct)
10/22/2021
NRC 2021 DBAI: Design Tornado Criteria in Unit 1 UFSAR
10/22/2021
21-DBAI U2 Intake Structure Multi. Conduit Covers
Missing
10/25/2021
21-DBAI U2 Intake Structure Valve Pit Room Severe
Rust
10/26/2021
21-DBAI U2 Intake Structure Conduit Pedestal Cracked
10/26/2021
21 DBAI-Error on Drawing 8770-G-878
10/27/2021
Documentation Discrepancy Regarding the Unit 1 Vacuum
Relief Setpoints
10/28/2021
21 DBAI Item # 0214 - Improper Cancellation of WR 94137532
10/29/2021
21 DBAI-U2 Support CW-3000-7004 for CW-11 Follow-
up Insp
10/29/2021
21 DBAI Update Proc with U2 Station Service Xfmr
Guidance
11/02/2021
21 DBAI-Improve WO Process to Remove Field
Equipment.
11/02/2021
Incorrect Statement in EQ Document Package
11/02/2021
Normal Radiation Dose Rates at Unit 1 FCV-25-8 Isolation
Valve
11/02/2021
Containment Vacuum Analysis Inconsistent With Technical
Specifications
11/03/2021
21 DBAI-U2 Intake Structure-Degraded Support Steel
11/03/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Electrical Conduit Covers Held with Zip-Ties
11/03/2021
21 DBAI-Untimely Reinspection of 2B3 480V MCC
11/03/2021
21 DBAI-U2-Pipe Sup. 2998-CW-3000-7001-ITEM#6 Bolt
Degraded
11/03/2021
21 DBAI-U1 Containment Vacuum Relief Calc Fouling
Factor
11/04/2021
Normal Operations Radiation Dose for EQ of Solenoid Valve
11/04/2021
21 DBAI-Completion of Structures Inspection Reports
11/04/2021
U2 ICW Pump Ground Cable
11/04/2021
Error in EQ Zone DOC PAC U1 15.2 and 1.3 for EQ
Components on FCV-25-7/8
11/09/2021
Add Note to Calculation 129154-M-0115
11/17/2021
Drawings
2998-24421 Sht.
of 37
ST. LUCIE UNIT 2 ROD CONTROL SYSTEM UPGRADE
POWER CABINET CONFIGURATION AND INSTALLATION
2998-24421, Sht.
of 37
ST. LUCIE UNIT 2 ROD CONTROL SYSTEM UPGRADE
POWER CABINET CONFIGURATION AND INSTALLATION
2998-24421, Sht.
and 37
ST. LUCIE UNIT 2 ROD CONTROL SYSTEM UPGRADE
POWER CABINET CONFIGURATION AND INSTALLATION
2998-G-085
Flow Diagram Instrument Air System
8770-12704
1/2" - 1878 Piston Check Valve
8770-12721
3/4" 1878 Socket Ends Carbon Steel Piston Check Valve
Non-Cobalt Trim
8770-3726
1/2" - 2" 600 #CS Piston Check Valves
M
8770-5655
in Piston Spring Oper Btfy Valve I-FCV-25-7 & 8
8770-5656
Cross Sect Btfy Valves I-FCV-25-7, 8, 9, 10, 11, 12, & 13
8770-5858
Cross Section ASME - P&V Code Standard Nuclear Class 2
N-SL-2FII Valve
8770-6530
Pist Spring Oper for Btly Valves I-FCV-25-7 & 8
8770-A-451-1000
Equipment Qualification Documentation Package
8770-B-327
Control Wiring Diagram: Diesel-Gen Fuel Oil Transfer Pump
1B
8770-G-878
HVAC - Control Diagrams - Sheet 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
Unit 1: Installation Of Air Filtration Device Upstream V18290
Convert Manual Pratt Butterfly Valve to AOV
U2: Replace Regulators Upstream of FCV-25-7 and FCV-
25-8
Unit 1 EDG Day Tank Fill Valve Relay
Engineering
Evaluations
EC295797_50-59
CEDMCS CAB C2 - Revise 120 VAC Power Source for UV
Relays
ENG-SPSL-08-
0164
Identification of Containment Isolation Valves Subject to
Technical Specification 3/4.6.3, "Containment Isolation
Valves"
JPN-PSL-SEIP-
93-049
Emergency Diesel Generator(EDG) Instrument Setpoint
Evaluation
PSL-ENG-LRAM-
00-095
SYSTEMS AND STRUCTURES MONITORING PROGRAM
- LICENSE RENEWAL BASIS DOCUMENT
PSL-ENG-SESS-
01-039
Scoping and Categorization of Air Operated Valves
Miscellaneous
21-31017
Certificate of Analysis: FPL Instrument Air sample results
10/14/2021
2998-2472
Vendor Manual - ITE Switch gear, Breakers/Components
8770-12712
1/2" - 2" 1878 lb Piston Lift Check Valves with Resilient Seat
Option
8770-12743
Design & Seismic Analysis 3/4" Class 1878 Carbon Steel
GB Piston Check Valve
8770-16809
Vendor Manual -U1/U2 480V Masterpact Breakers
8770-6250
Velan Valves and Maintenance Instructions
8770-8717
Henry Pratt Butterfly Valves
DBD-480V-AC-2
480 VAC DISTRIBUTION SYSTEM Design Basis Document
DBD-CCW-1
Component Cooling Water System
DBD-CCW-2
Component Cooling Water System
DBD-CNTMT-1
Containment Systems
ER-M-100-2002-
F05
Fleet Maintenance Rule Scoping Document
FLO-2998.114
EBASCO Specification Rubber Seated Butterfly Valves
FPL-1
Quality Assurance Topical Report
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operability
Evaluations
2-AOP-22.01
Rapid Downpower
Procedures
0-PME-100.08
Agastat E7000 Series Timing Relay Testing Procedure
1-ADM-09.23
Time Critical Operator Actions and Time Sensitive Actions
Program
1-AOP-01.13
Natural Circulation Cooldown
1-AOP-18.01
Instrument Air Malfunction
1-AOP-68.01
Loss of Containment Integrity/Air Locks
1-AOP-99.02
Station Blackout While Shutdown
1-ARP-01-F00
Control Room Panel F RTGB-102
1-EOP-09
Loss of Offsite Power/Loss of Forced Circulation
LOOP/LOFC
1-EOP-99
Appendices/Figures/Tables/Data Sheets
1-GOP-123
Turbine Shutdown - Full Load to Zero Load
1-GOP-201
Reactor Plant Startup - Mode 2 to Mode 1
1-GOP-203
Reactor Shutdown
1-GOP-302
Reactor Plant Startup - Mode 3 to Mode 2
1-GOP-303
Reactor Plant Heatup - Mode 3 < 1750 to Mode 3 > 1750
1-GOP-305
Reactor Plant Cooldown - Hot Standby to Cold Shutdown
1-GOP-403
Reactor Plant Heatup - Mode 4 to Mode 3
1-GOP-504
Reactor Plant Heatup - Mode 5 to Mode 4
1-NOP-18.41
Instrument Air System Operation
1-NOP-25.05
Containment Ventilation Systems
1-NOP-59.01B
1B Emergency Diesel Generator Standby Lineup
1-NOP-59.02B
1B Emergency Diesel Generator Operations
1-NOP-99.07
Operations Hard Cards
1-ONP-01.03
Plant Condition 3 Shutdown Cooling in Operation - No
Reduced Inventory
1-ONP-01.04
Plant Condition 4 Shutdown Cooling in Operation - Reduced
Inventory Operations
1-OSP-100.27
Schedule of Periodic Tests, Checks and Calibrations
1-OSP-18.01
INSTRUMENT AIR ACCUMULATOR TESTS
1-OSP-68.02
Local Leak Rate Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-OSP-99.29
Surveillance Tracker
1-PMI-25.27
P-25-1B and P-25-13B, Containment to Annulus Channel B
Differential Pressure Calibration
2-ADM-09.23
Time Critical Operator Actions and Time Sensitive Actions
Program
2-AOP-01.08
RCS Leakage Abnormal Operations
2-AOP-01.10
Pressurizer Pressure and Level
2-AOP-01.13
Natural Circulation Cooldown
2-AOP-09.01
Feedwater Control System Abnormal Operations
2-AOP-14.01
Component Cooling Water Abnormal Operations
2-AOP-18.01
Instrument Air Malfunction
2-AOP-21.03A
2A Intake Cooling Water System Header
2-AOP-47.01B
Loss of a Safety Related AC Bus - Train B
2-AOP-49.02
20V Instrument AC System (Class 1E) Abnormal Operation
2-AOP-99.01
Loss of Technical Specification Instrumentation
2-EOP-01
Standard Post Trip Actions SPTA
2-EOP-03
Loss of Coolant Accident (LOCA)
2-EOP-04
Steam Generator Tube Rupture
2-EOP-99
Appendices/Figures/Tables/Data Sheets
2-GOP-123
Turbine Shutdown - Full Load to Zero Load
2-GOP-201
Reactor Plant Startup - Mode 2 to Mode 1
133
2-GOP-203
Reactor Shutdown
2-GOP-302
Reactor Plant Startup - Mode 3 to Mode 2
2-GOP-303
Reactor Plant Heatup - Mode 3 < 1750 to Mode 3 > 1750
2-GOP-305
Reactor Plant Cooldown - Hot Standby to Cold Shutdown
2-GOP-305
Reactor Plant Cooldown - Hot Standby to Cold Shutdown
2-GOP-403
Reactor Plant Heatup - Mode 4 to Mode 3
2-GOP-504
Reactor Plant Heatup - Mode 5 to Mode 4
2-NOP-99.07
Operations Hard Cards
2-ONP-01.03
Plant Condition 3 Shutdown Cooling in Operation - No
Reduced Inventory
2-ONP-01.04
Plant Condition 4 Shutdown Cooling in Operation - Reduced
Inventory Operations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-OSP-100.27
Schedule of Periodic Tests, Checks and Calibrations
105
ADM-09.25
Surveillance Frequency Control Program
ADM-17.32
Structures Monitoring Program
ADM-29.01A
Inservice Testing (IST) Program for Pumps and Valves
ADM-68.01
Containment Leakage Rate Testing Program
Design Control Program
Operability Determinations/Functionality Assessments
Design Change Packages
Air Operated Valve Program
Air Operated Valve Program Implementation
Maintenance Rule Program Administration
IP-ENG-001
Standard Design Process
C
OP-1-0010125A
Surveillance Data Sheets
199
OP-2-0010125A
Surveillance Data Sheets
218
Conduct of Operations
STD-C-009
Seismic Technical Evaluation - Replacement Items and New
Designs
STD-M-005
ANSI/ASME Code Reconciliation for Replacement Materials,
Parts, & Components
Conduct of Simulator Training and Evaluation
TR-AA-230-1007-
F13
Simulator Exercise Guide, Three Column
Self-Assessments AR 2359881 -
Assessment of SSMP Walkdowns
AR# 2251726
NRC IN 2018-03: Failure to Meet Technical Specifications
for Changing Plant Conditions.
05/01/2018
Work Orders
Work Order (WO)
2009385, 40496750, 40499133, 40503590, 40565248,
40571871, 40696319, 40696501, 40696511, 40696522,
40744465, 40746926, 40757846, 40758145, 40758147,
40758149, 40758701, 40758710, 40772657, 40772658,
40772659, 40046912, 40555939, 40572603, 40615761,
40618195, 40634403, 40664727, 40680001, 40693891,
40706737, 40722774, 40739171, 40752039, 40760691,
40760524