ML24354A139
| ML24354A139 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/19/2024 |
| From: | Masters A NRC/RGN-II/DORS/EB1 |
| To: | Coffey B Florida Power & Light Co |
| References | |
| IR 2024010 | |
| Download: ML24354A139 (14) | |
Text
Bob Coffey Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company 700 Universe Blvd.
Mail Stop: EX/JB Juno Beach, FL 33408
SUBJECT:
ST. LUCIE PLANT UNITS 1 AND 2 - NRC QUADRENNIAL FOCUSED ENGINEERING INSPECTION (FEI) AGE RELATED DEGRADATION REPORT 05000335/2024010 AND 05000389/2024010
Dear Bob Coffey:
On December 18, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at St. Lucie Plant Units 1 and 2 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at St. Lucie Plant Units 1 and 2.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at St. Lucie Plant Units 1 and 2.
December 19, 2024
B. Coffey 2
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, Anthony D. Masters, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket Nos. 05000335 and 05000389 License Nos. DPR-67 and NPF-16
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Masters, Anthony on 12/19/24
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DRS RII/DRS NAME T. Fanelli A. Masters DATE 12/19/24 12/19/24
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000335 and 05000389 License Numbers:
DPR-67 and NPF-16 Report Numbers:
05000335/2024010 and 05000389/2024010 Enterprise Identifier:
I-2024-010-0049 Licensee:
Florida Power and Light Company Facility:
St. Lucie Plant Units 1 and 2 Location:
Jensen Beach, FL.
Inspection Dates:
November 18, 2024 to December 18, 2024 Inspectors:
T. Fanelli, Senior Reactor Inspector C. Franklin, Reactor Inspector G. Ottenberg, Senior Reactor Inspector J. Rolland, Mechanical Engineer Approved By:
Anthony D. Masters, Chief Engineering Br 1 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC Quadrennial Focused Engineering Inspection (FEI) of Age Related Degradation at St. Lucie Plant 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 Loss of Design Control for DC switchgear Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000335,05000389/2024010-01 Open/Closed
[H.5] - Work Management 71111.21N.
04 The NRC identified a finding of very low safety significance (Green) and an associated Non-Cited Violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, for the licensees failure to control the U1 and U2 direct current (DC) switchgear design in accordance with the design control program.
Additional Tracking Items None.
3 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.04 - Age-Related Degradation Age-Related Degradation (8 Samples)
(1)
Vital DC Switchboards (2)
Class 1E Underground Cables-Conduits (3)
Emergency Diesel Generator flexible hoses, ducts, and couplings (4)
Reactor Coolant System and Main Steam System Snubbers (5)
Auxiliary Feedwater System Piping (6)
Intake Piping from Intake Cooling Water to Component Cooling Water and Turbine Cooling Water (7)
Unit 1: Component Cooling Water Pumps (8)
Unit 2: Containment Spray System INSPECTION RESULTS Loss of Design Control for DC switchgear Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000335,05000389/2024010-01 Open/Closed
[H.5] - Work Management 71111.21N.0 4
The NRC identified a finding of very low safety significance (Green) and an associated Non-Cited Violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, for the licensees failure to control the U1 and U2 direct current (DC) switchgear design in accordance with the design control program.
==
Description:==
The original model molded case circuit breakers (MCCBs) are no longer available, the site used Item Equivalent Evaluations (IEE) to procure and install new model MCCBs into the station Class 1E DC switchgear. The IEEs evaluated the acceptability of replacing type HFB breakers with HFD type breakers in safety related DC panels. It concluded that an engineering change was required prior to installing the new breakers to ensure appropriate calculations were evaluated and revised as needed prior to installation.
Although the MCCBs were functionally equivalent, they were not identical, in that the tripping characteristics were not the same, thus affecting important electrical design calculations.
These calculations would need to be updated and verified for adequate system designs.
Calculations for Electrical Coordination Studies examines the site electrical power systems
4 for selective coordination. Calculations for 125V DC System ETAP Models & Analyses performs load flow, voltage drop, battery sizing and short circuit analysis for the safety related DC systems. These calculations were not verified against the new MCCB designs, and in addition, the databases that tracks what MCCB is installed in each location was not updated with the correct information.
The inspection found that since approximately 2015 more than 70 MCCBs had been installed without completing the engineering design changes to the DC systems. The inspectors determined that the licensees failure to meet the site design control program affected the safe design of the Class 1E DC systems.
Corrective Actions: The licensee entered this issue into the corrective action program, and separate corrective action assignments would be generated to request updating the identified documents and equipment database NAMS panels and verify the design of the DC systems.
Corrective Action References: Action Requests (ARs) 02502554 and 02502564 Performance Assessment:
Performance Deficiency: The licensees failure to control the U1 and U2 direct current (DC) switchgear design in accordance with the design control program was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to ensure that MCCB trip characteristic could not impede or delay the safe operation of the DC power system affected the reliability and capability of the systems that rely on DC power to perform their safety function.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Exhibit 2
- Mitigating Systems Screening Questions, Item A. The finding was a deficiency affecting the design or qualification of a mitigating SSC, and it maintain its operability or PRA functionality which screened to Green.
Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities.
The organization did not implement a process of planning, controlling, and executing work activities affecting the Class 1E power systems such that nuclear safety was the overriding priority.
Enforcement:
Violation: Title 10 CFR 50, Appendix B, Criterion III, Design Control, requires, in part, that the design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
5 Contrary to the above, the licensee failed to verify the design of the Class 1E DC power system by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program. Specifically, the licensee failed to verify the DC system performance after changing the design of the DC power system protection devices.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On December 18, 2024, the inspectors presented the NRC Quadrennial Focused Engineering Inspection (FEI) Age Related Degradation results to Mr. Robert Craven and other members of the licensee staff.
6 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Corrective Action Documents AR 2486899, AR 01902957, AR 2036040, AR 2076003, AR 02095478, AR 2429763, AR 2483373, AR 2362262, AR 2403868, AR 2403929, AR 2404011, AR 2404013, AR 2488777, AR 2437896 AR 02502554 U1 MCCB Config Mgmnt AR 02502564 U2 MCCB Config Mgmnt AR 02502735 Dwg Error AR 02503010 NRC Identified Issue: Evaluate MSLB Temperature per MN-2.91 AR 02503189 1B EDG Air Intake To EDG Flex Duct Excessive Offset AR 2502038 (U1 SH 21334 Degraded Flange Studs & Nuts)
AR 2502039 (U1 Cw105 Flange - Cs Bolt Instead of Ss)
[NRC ARD Insp] Root Valves V09125 & V09126 Bonnet Corrosion AR 2502153
[NRC ARD Insp] Vent Line Caps Not Installed Post Sl2-28 AR 2502175
[NRC ARD Insp] Condensate Line C-52 In-Contact With Grating AR 2502268 NRC PSL Eng 2B EDG Wlkdown AR 2502273 NRC ARD Insp-2A EDG 2A1 DC Turbo Lube Oil Pp AR 2502289 NRC ARD Insp-1A2 Air Start MTR Vent Hose AR 2502294 NRC ARD Insp-1B1 Air Start MTR Vent Hose 71111.21N.04 Corrective Action Documents Resulting from Inspection AR 2502296 NRC ARD Insp-2A1 Air Start MTR Vent Hose
7 Inspection Procedure Type Designation Description or Title Revision or Date AR 2502297 NRC ARD Insp-1A1 Soak-back Pp MTR Fan Cover AR 2502300 NRC ARD Insp-2A1 Soak-back PP Disch Line AR 2502308 2A EDG Flex Hose Offset AR 2502951 Cosmetic Damage AR 2503015 Evaluate Accident Conditions Snubbers 037061-JL-LD-1 JL Breaker Modification Rev 3 2998-A-451-1000 St. Lucie Plant Unit No 2 Equipment Qualification Documentation Package Rev 15 2998-G-080 Sht 2B Flow Diagram Feedwater & Condensate Systems Rev 40 2998-G-082 P&ID Circulating & Intake Cooling Water System Rev. 67 2998-G-088 P&ID Containment Spray and Refueling Water Systems Rev. 52 2998-G-170 Yard Piping Sheet No 1 Rev 24 8770-A-451-1000 St. Lucie Unit No 1 Equipment Qualification Documentation Package Rev 16 8770-G-080 Sht 4 Flow Diagram Feedwater & Condensate Systems Rev 46 8770-G-082 P&ID Circulating & Intake Cooling Water System Rev. 3 Drawings 8770-G-170 Sht 2 Yard Piping Sheet No 1B Rev 17 EC 297078 125V DC Bus 1B Breaker Replacements for CKT 29, 30 and 32 Rev 0 EC 299739 125V DC BUS 2AB Rev 0 Engineering Changes EC284197 PSL-2FSE-08-001 Unit 2 Electrical Coordination Study; Reg Guide 1.63, Reg Guide 1.75 And Appendix R Validation Rev 0 02481032-03 PLS Testing of Inaccessible Cables 12/02/2024 ERC-037061-JL-1 JL Circuit Breaker Equivalency Evaluation Rev 1 EVAL-PSL 03282 Unit 2 Condensate System JPE-M-87-103 Snubber Acceptance Criteria Rev 20 Engineering Evaluations Molded Case Circuit Breaker Time Current Curves HFB 15, HFB 30, HFB 50, HFB 70, HFB 100, ITE CE 15A, ITE CE 20A, ITE JL 350A
8 Inspection Procedure Type Designation Description or Title Revision or Date QR-037061-2 Qualification Report for NLI JL Retrofit Breakers Rev1 LISEGA Snubber Replacement Booklet LISEGA Information Bulletin August 24, 2004 07/30/2007 ADAMS ML18040A267 L-2018-042, Snubber Program Plan Submittal 02/09/2018 ADAMS ML24227A633 L-2024-133, Snubber Program Plan Submittal 08/14/2024 DBD-AFW-1 Auxiliary Feedwater System Rev 8 DBD-AFW-2 Auxiliary Feedwater System Rev 12 ENG-CSI-XCI-100 External Corrosion (XCI) Monitoring Program for Insulated Piping for PSL and PTN License Renewal Rev 6 ENG-LRAM 023 CST Cross Connect Buried Pipe Inspection License Renewal Basis Document Rev 3 EVAL-PSL 03282 CNDSR 2A (AR 02488777) l PSL Condenser Extent of Condition (EOC): CNDSR 2B/1A/1B Letter Service Life of LISEGA Hydraulic Snubbers 08/01/2001 Maintenance Rule Event 120VA VITAL SYSTEM - EVT-49-2024-49935 04/13/2024 Maintenance Rule Event DC system event-EVT-50-2023-48964 11/20/2023 Maintenance Rule Event DC system event-EVT-50-2024-49752 03/28/2024 OSP-73.01 Guidelines for the Implementation of the Snubber Inspection and Test Program Rev 16 PMC-19-006604 Aux Feedwater and Condensate Pipe trench Inspections (FREQ CHANGE SL1-33)
PMC-20-007345 Add Structures Inspection Tasks to Model WOs for PMRQs 83579-01 & 83581-01 CST & AFW Pipe Trenches PMCR 2109388 Unit 2 CST & AFW Piping Inspection in the Trenches 02/11/2016 03/07/2016 Miscellaneous PMRQ 00083579-01 Unit 2 CST & AFW Piping Inspection in the Trenches
9 Inspection Procedure Type Designation Description or Title Revision or Date PSL-ENG-LRAM-00-082 License Renewal Aging Management Review-Diesel Generator Cooling Water System Rev 3 PSL-ENG-LRAM-00-084 St. Lucie Units 1 and 2 License Renewal Aging Management Review-Diesel Generator Air System Rev 4 PSL-ENG-LRAM-00-093 Chemistry Control Program-License Renewal Basis Document Rev 10 PSL-ENG-LRAM-00-096 Periodic Surveillance and Preventive Maintenance Program-License Renewal Basis Document Rev 16 PSL-ENG-LRAM-00-114 Pipe Wall Thinning Inspection Program License Renewal Basis Document Rev 8 PSL-ENG-SECS-05-053 Inspection Procedures and Repair Contingencies for the Refueling Water Tank Bottom Liner Rev. 1 Q3-2024 Snubber Program Health Report QP-037061-2 Test plan JL Circuit Breaker Qualification REV-0 SL1-31 Outage Report 11/04/2024 SL1-32 Outage Report 03/29/2024 SL2-27 Outage Report 04/14/2023 SL2-28 Outage Report 09/25/2024 SPEC-M-023 ICW & CW System Inspection and Repair for St. Lucie Units 1 and 2 Rev. 14 Spec-M-081 CCW Heat Exchangers Tube Integrity Inspection, PTN Units 3 and 4 and PSL Units 1 and 2 Rev. 1 Specification DS30-001 LISEGA Series 30 Snubbers and 33 Extensions Rev 3 Specification DS30-002 LISEGA Series 30 Snubbers Rev 0 Specification MN 2.91 Hydraulic Snubbers for Piping Rev 2 Specification MN 3.29 Design Specification for Steam Generator Hydraulic Snubbers for St. Lucie Plant Units 1 & 2 Rev 1 Spreadsheet U1 DC MCCB Discrepancies 12/02/2024 Spreadsheet U2 DC MCCB Discrepancies 12/02/2024 VTM 2998-7434 I/M Diesel Generator Rev 48 VTM 8770-6703 Emergency Diesel Generator System-General Rev 33
10 Inspection Procedure Type Designation Description or Title Revision or Date Description, Operation and Maintenance 0-CMM-21.06 Intake Cooling Water (ICW) System Piping Inspection and Repair Rev. 11 0-COP-05.04 Chemistry Department Surveillances and Parameters Rev 123 0-GME-53.01 Grounding or Testing of High Voltage (4.16 or 6.9 kV)
Loads Rev 21 0-GME-53.02 Grounding or Testing of High Voltage (4.16 or 6.9 kV)
Switchgear Buses for Maintenance Rev 9 0-PME-75.03 Preventive Maintenance Procedure for Corrpro Constant Potential Cathodic Protection Rectifiers Rev. 2 1-PME-75.01 Preventive Maintenance Procedure for Surveying Cathodic Protection Systems Rev, 9 2-ISP-100.01 ASME Section Xi Pressure Test Procedure for Class 2 &
3 Systems Rev. 31 2-PME-75.01 Preventive Maintenance Procedure for Surveying Cathodic Protection Systems Rev. 8 ADM-17.32 Structures Monitoring Program Rev. 14 ADM-17.33 License Renewal Systems / Programs Monitoring Rev. 15 ADM-17.33 License Renewal Systems / Programs Monitoring Rev 15 ADM-29.01A Inservice Testing (IST) Program for Pumps And Valves Rev. 35 CY-SL-108-0001 Condenser Tube Leak or Air Leak Rev 5 EN-AA-100 Design Control Program Rev 11 ENG-CSI-XCI-100 External Corrosion (XCI) Monitoring Program For Insulated Piping For PSL and PTN License Renewal Rev. 6 ER-AA-106 Cable Condition Monitoring Program Rev 8 ER-AA-119 Fleet Snubber Program Rev 9 ER-AA-119-1000 Snubber Program Procedure Rev 10 IM-037061-2 Installation Manual for NLI JL Retrofit Breakers Rev.1 PSL ENG-LRAM-00-110 Galvanic Corrosion Susceptibility Inspection Program License Renewal Basis Document Rev. 8 PSL-ENG-LRAM-00-067 License Renewal Aging Management Review -
Containment Spray System Rev. 2 Procedures PSL-ENG-LRAM-00-093 Chemistry Control Program - License Renewal Basis Document Rev. 10
11 Inspection Procedure Type Designation Description or Title Revision or Date PSL-ENG-LRAM-00-095 Systems and Structures Monitoring Program - License Renewal Basis Document Rev. 14 PSL-ENG-LRAM-00-096 Periodic Surveillance and Preventative Maintenance Program - License Renewal Basis Document Rev. 16 PSL-ENG-LRAM-00-114 Pipe Wall Thinning Inspection Program License Renewal Basis Document Rev. 8 PSL-ENG-LRAM-00-115 Intake Cooling Water System Inspection Program -
License Renewal Basis Document Rev. 9 PSL-ENG-LRAM-02-029 Containment Cable Inspection Program - License Renewal Basis Document Rev 6 PSL-ENG-SERS-16-001 PSL Asset Management Plan for the Underground Piping and Tank Integrity Program (UPTIP)
Rev, 2 Work Orders Work Orders 40055265, 4005526101, 4015329901, 40420932, 40767873, 40775270-01, 40776490-01, 40845589-01, 40847368-01, 40712636-01, 40750329-04, 4014873-01, 40147878-01, 40084246-01, 40104763-01, 40657785-01, 40738772-01, 40745879-01, 40817296-01, 40627600-01, 40717680-01, 40717680-04, 40820201-01, 40920201-02, 40353539-01, 40876711-01, 40876711-02