ML25017A264
| ML25017A264 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/22/2025 |
| From: | Michael Mahoney NRC/NRR/DORL/LPL2-2 |
| To: | Coffey B Florida Power & Light Co |
| Mahoney M, NRR/DORL/LPL2-2 | |
| References | |
| EPID L-2023-LLA-0161 | |
| Download: ML25017A264 (1) | |
Text
January 22, 2025 Robert Coffey Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT:
TURKEY POINT NUCLEAR GENERATING, UNIT NOS. 3 AND 4 -
REGULATORY AUDIT
SUMMARY
RELATED TO REVIEW OF LICENSE AMENDMENT FOR EXTENSION OF SURVEILLANCE INTERVALS TO FACILITATE A 24-MONTH FUEL CYCLE (EPID L-2023-LLA-0161)
Dear Robert Coffey:
By application dated November 15, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23320A028), as supplemented by letters dated February 9, October 3, 31, and November 12, 2024 (ADAMS Accession Nos. ML24040A190, ML24278A038, ML24305A144, and ML24317A059, respectively), Florida Power & Light Company (FPL or the licensee), submitted a license amendment request (LAR) to revise the Turkey Point Nuclear Generating,Unit Nos. 3 and 4 (Turkey Point), technical specifications (TS).
The proposed amendments would revise the Turkey Point licensing basis by incorporating advanced fuel features (e.g., AXIOM cladding, ADOPTTM fuel pellets, and a PRIMETM fuel skeleton) to extend TS surveillance intervals, modify TS Allowable Values, and make conforming changes to the Updated Final Safety Analysis Report to facilitate a transition to 24-month fuel cycles.
The licensee also submitted technical report Westinghouse Commercial Atomic Program (WCAP)-18888-P, Westinghouse Setpoint Methodology for Protection Systems Turkey Point Units 3 & 4 24 Month Fuel Cycle, Revision 0 (ML24040A191 - Proprietary). WCAP-18888-P was prepared to replace older, previously NRC-approved setpoint methodologies and combine the earlier methods into one comprehensive method for calculating TS controlled instrument channel setpoints.
To enhance the review of the licensees request, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a virtual regulatory audit that included discussions with your staff on April 30, June 17, June 27, September 9 and September 20, 2024. A summary of the regulatory audit is enclosed. The NRC staff did not identify any significant issues during the audit.
If you have any questions, please contact me at (301) 415-3867, or Michael.Mahoney@nrc.gov.
Sincerely,
/RA/
Michael Mahoney, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosure:
Regulatory Audit Summary cc: Listserv
Enclosure REGULATORY AUDIT
SUMMARY
REGARDING LICENSE AMENDMENT TO TRANSITION TO A 24-MONTH FUEL CYCLE FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING, UNIT NOS. 3 AND 4 DOCKET NO. 50-250 AND 50-251
1.0 BACKGROUND
A regulatory audit is an activity undertaken by the U.S. Nuclear Regulatory Commission (NRC) staff to examine and evaluate licensee information with the intent to gain an understanding of, verify, or identify information that will require docketing to support the basis of a licensing or regulatory decision.
By application dated November 15, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23320A028), as supplemented by letters dated February 9, October 3, 31, and November 12, 2024 (ADAMS Accession Nos. ML24040A190, ML24278A038, ML24305A144, and ML24317A059, respectively), Florida Power & Light Company (FPL or the licensee), submitted a license amendment request (LAR) to revise the Turkey Point Nuclear Generating, Unit Nos. 3 and 4 (Turkey Point), technical specifications (TS).
The proposed amendments would revise the Turkey Point licensing basis by incorporating advanced fuel features (e.g., AXIOM cladding, ADOPTTM fuel pellets, and a PRIMETM fuel skeleton) to extend TS surveillance intervals, modify TS Allowable Values, and make conforming changes to the Updated Final Safety Analysis Report to facilitate a transition to 24-month fuel cycles.
The licensee also submitted technical report Westinghouse Commercial Atomic Program (WCAP)-18888-P, Westinghouse Setpoint Methodology for Protection Systems Turkey Point Units 3 & 4 24 Month Fuel Cycle, Revision 0 (ML24040A191 - Proprietary). WCAP-18888-P was prepared to replace older, previously NRC-approved setpoint methodologies and combine the earlier methods into one comprehensive method for calculating TS controlled instrument channel setpoints.
The NRC staff performed a preliminary review of the license amendment requests and determined that a regulatory audit would assist in the timely completion of the review. The NRC staff conducted a virtual regulatory audit that included a discussions with the licensee on April 30, June 17, June 27, September 9, and September 20, 2024. The audit plan was provided to the licensee on April 11, 2024 (ML24102A169).
2.0 AUDIT ACTIVITIES AND OBSERVATIONS The remote audit was conducted using web-conferencing capabilities. The purpose of the audit was to (1) confirm internal licensee information that supports statements made in the LAR, and (2) determine whether the information included in the documents is necessary to be submitted to support a safety conclusion.
Discussions on the topics identified in the attachment of the audit plan were held with the licensee during an audit calls conducted on April 30, June 17, June 27, September 9 and September 20, 2024. The NRC staff assessed the information provided during the audit to determine whether additional information would be needed to support a regulatory finding, and therefore, would need to be submitted for NRC review.
3.0 AUDIT PARTICIPANTS NRC FPL Westinghouse Michael Mahoney Jarrett Mack Jean-Dominique LeGarrec Santosh Bhatt Yacine Faouzi James Smith Richard Fu Emilio Fuentes Amy Colussy Ahsan Sallman Ralph Jaskiewicz Kyle Shelton Joseph Messina Wendy Zumbo David Huegel William Roggenbrodt Jacob Fauber Sean Kinnas Khoi Nguyen Patrick Hahn Kevin Barber Derek Scully Heather McMillen Nicholas Soliz Douglas Hake Fanta Sacko Baster Durham Perry Buckberg Michael Orner Andrew Sheaffer Michael Wenner Christopher Treleani Christopher Briggs Lylliam Sekkat Richard Karapandi Curt Ciocca John Moorehead Jerrod Ewing 4.0 LIST OF DOCUMENTS PROVIDED ON THE ELECTRONIC PORTAL FPL provided the following supporting documents on the Certrec portal:
Drawing 5614-J-839A SH 02-EC298462, Instrument Setpoints Drawing 5614-J-839 SH 02-EC298462, Instrument Setpoints Drawing 5614-J-839A SH 03-EC298462, Instrument Setpoints Drawing 5614-J-839A SH 03-EC298462, Instrument Setpoints Drawing 5613-J-839 sheet 1, Instrument Setpoints Drawing 5613-J-839 sheet 2, Instrument Setpoints Drawing 5613-J-839 sheet 3, Instrument Setpoints Drawing 5613-J-839 sheet 4, Instrument Setpoints Drawing 5614-J-839A sheet 2, Instrument Setpoints Surveillance Maintenance Procedure 3-SMI-072.01, Revision 14, P-3-458, P-3-474, P-3-484 and P-3-494 Steam Pressures Channel Calibration, Protection Chanell II Drawing 5610-J-844 sheet 10A, Steam Break Protection (P-474, 484, 494)
Drawing 5613-J-839A sheet 2, Instrument Setpoints Drawing 55613-M-430-268, Loop A Steam Break Protection Channel II, III, & IV Calculation 21701-566-J03, Pressure Transmitter Scaling Calculation in Support of Information Notice 91-75 Surveillance Maintenance Procedure 3-SMI-071.02A, Revision 11, Steam Generator 3A Level (Narrow Range) Protection Set I Loop L-474 Channel Calibration WCAP-17283-P, Revision 0, Westinghouse Setpoint Methodology For Protection Systems Turkey Point Units 3 & 4 (Consolidation of WCAP-1745, Revisions 0 and 1 with WCAP-17070-P, Revision 0)
WCAP-17283-P, Revision 1, Westinghouse Setpoint Methodology For Protection Systems Turkey Point Units 3 & 4 (Consolidation of WCAP-1745, Revisions 0 and 1 with WCAP-17070-P, Revision 3)
WCAP-17283-P, Revision 2, Westinghouse Setpoint Methodology For Protection Systems Turkey Point Units 3 & 4 (Consolidation of WCAP-1745, Revisions 0 and 1 with WCAP-17070-P, Revision 3)
Westinghouse and FPL provided the following supporting documents on the Westinghouse Electronic Portal during the virtual audit.
CN-SCS-22-7, Revision 0, Turkey Point Unit 3 & 4 24-Month Fuel Cycle Extension and 48-Month Surveillance Extension Drift Evaluation CN-SCS-22-7-R0-ASMT-1, Discovery of Legacy Errors & Re-Evaluation of Containment Pressure Drift Analysis CN-CPS-08-75, Revision 4, Tavg Rod Control RTDP, DNB, and Tavg Low-Low, Safety Injection, Steam Line Isolation Uncertainty Calculations for Turkey Point Units 3 and 4 CN-CPS-08-77, Revision 3, Pressurizer Pressure - Control, High and Low Reactor Trip, and Low Safety Injection Uncertainty Calculations for Turkey Point Units 3 & 4 CN-CPS-08-78, Revision 2, Pressurizer Water Level - Control Uncertainty, High Reactor Trip Calculations for Turkey Point Units 3 & 4 CN-CPS-08-85, Revision 3, High Steam Flow and Steam/Feedwater Flow Mismatch Setpoint Calculations for Turkey Point Units 3 & 4 CN-CPS-08-87, Turkey Point Units 3 & 4 Overtemperature T and Overpower T Uncertainty Calculation CN-CPS-09-15, Revision 2, NIS Power Range Neutron Flux - High and Low Reactor Trip for Turkey Point Units 3 and 4 CN-CPS-09-18, Revision 2, Steamline Pressure - Low (SI) for Turkey Point Units 3 and 4 CN-CPS-09-33, Revision 3, Turkey Point (FPL) Units 3 and 4 Narrow Range Steam Generator Level Control/Protection Uncertainty Calculations CN-CPS-09-33-R3-ASMT-1, Discovery of Legacy Errors & Re-Evaluation of Steam Generator Level Process Measurement Allowance (PMA) terms when using GENF 1.2.0 for Steam Generator Level trip and control functions for Turkey Point Units CN-CPS-09-33-R3-ASMT-2, Discovery of Legacy Errors & Re-Evaluation of Steam Generator Level Process Measurement Allowance (PMA) terms when using GENF 1.2.0 for Steam Generator Level trip and control functions for Turkey Point Units CN-SCS-23-11, Revision 0, NIS Intermediate and Source Range Neutron Flux Reactor Trip for Turkey Point Units 3 and 4 CN-SCS-23-3, Revision 0, Containment Pressure - High / Safety Injection and High-High / Spray for Turkey Point Units 3 & 4 CN-SCS-23-6, Revision 0, Turkey Point Units 3 & 4 Technical Specification Containment Particulate and Gaseous Radiation Setpoints CN-SCS-23-7, Revision 0, Turkey Point Units 3 & 4 Technical Specification Underfrequency Setpoints CN-SCS-23-8, Revision 0, Turkey Point Units 3 & 4 Technical Specification Undervoltage Setpoints CN-SCS-23-9, Revision 0, High Differential Steam Pressure Between Steam Header and Steam Generator Line, SI for Turkey Point Units 3 & 4 CN-SUA-10-22, Revision 2, Turkey Point Units 3 & 4 Emergency Trip Header Low Pressure Reactor Trip Uncertainty Calculation CE-23-143, Revision 1, Attachment 1, Turkey Point Units 3 & 4 24-Month Fuel Cycle Transition Fuel Rod Design Engineering Report Input FPLM-REAC-CN-AA-00001, Revision 1, Reactor Pressure Vessel Neutron Exposure Evaluation in Support of the Transition to 24-Month Fuel Cycles at Turkey Point Unit 3 and Unit 4 of FPLM-LOCA-TR-AA-000001, Revision 0, Engineering Summary Report of the Turkey Point Units 3 and 4 (FPL/FLA) 24-Month Fuel Cycle Transition Loss-of-Coolant Accident (LOCA) Analysis with the FULL SPECTRUM LOCA (FSLOCA)
Evaluation Model Methodology FPLM-LOCA-TM-AA-000007, Revision 0, Turkey Point Units 3 and 4 (FPL/FLA) 24-Month Fuel Cycle Transition: Post-LOCA Long Term Cooling Engineering Report Input FPLM-TANL-TM-AA-000010, Revision 1, Turkey Point Units 3 and 4 Non-LOCA Input to the 24-Month Cycles Engineering Report FPLM-TANL-TM-AA-000010, Revision 1, Turkey Point Units 3 and 4 Non-LOCA Input to the 24-Month Cycles Engineering Report FPLM-TSPS-TM-L9-000002, Revision 0, Turkey Point Nuclear Plant, Units 3 and 4 GL-91-04 Non-Calibration and Calibration Without Setpoints SR Evaluation Review Summary WCAP-17070-P, Revision 3, Westinghouse Setpoint Methodology for Protection Systems Turkey Point Units 3 & 4 (Power Uprate to 2644 MWt - Core Power)
CE-23-114, Revision 0, Attachment 1, Turkey Point Units 3 and 4 24-Month Cycle Transition Engineering Report Input - THD Section 5.0 RESULTS OF THE AUDIT As a result of the audit, the NRC staff gained a better understanding of information in the LAR.
Requests for additional information (RAIs) were issued to the licensee on September 6 and October 8, 2024 (ML24250A085 and ML24282A672, respectively). The licensee provided a response to the RAIs by letters dated October 3 and October 31,2024 (ML24278A040 [Not Publicly Available] and ML24305A144, respectively).
ML25017A264 NRR-106 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NAME MMahoney ABaxter DWrona DATE 1/16/2025 1/21/2025 1/22/2025 OFFICE NRR/DORL/LPL2-2/PM NAME MMahoney DATE 1/22/2025