L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report
| ML24109A010 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/17/2024 |
| From: | Rasmus P Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-2024-064 | |
| Download: ML24109A010 (1) | |
Text
April 17, 2024 L-2024-064 10 CFR 50.46 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Re: Florida Power & Light Company St. Lucie Unit 2, Docket No. 50-389
10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report
Pursuant to 10 CFR 50.46(a)(3)(ii), this letter contains the 30-day report for the Florida Power &
Light's St. Lucie Nuclear Plant, Unit 2, for the emergency core cooling system analysis performed by Framatome, described in the attachment to this letter.
A legacy error was identified in analytical inputs for the RCP homologous curves that impacts both the Realistic Large-Break (RLB) and the Small-Break (SB) LOCA analyses.
As the reported error is of a 0°F impact, the peak cladding temperature (PCT) continues to remain within the limits. However, as the cumulative PCT change already exceeds 50 °F for the SBLOCA analysis, a 30-day 1 OCFR50.46 report must be issued. The cumulative change for the RLBLOCA remains under 50 °F and therefore no report for RLBLOCA is attached. An evaluation of the reported error has concluded that re-analysis is not required.
This letter contains no new or revised regulatory commitments.
Should you have any questions regarding this report, please contact Mr. Kenneth Mack, Fleet Licensing Manager, at (561) 904-3635.
Very truly yours,
~asmus ~177 ~
General Manager, Regulatory Affairs Florida Power & Light Company
Attachment ( 1)
cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant USNRC Senior Resident Inspector, St. Lucie Nuclear Plant
Florida Power & Light Company
6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2024-064 10 CFR 50.46 Attachment 1 Page 1 of 1 St. Lucie Unit 2 Small Break LOCA PCT 30-Day Report
Evaluation Methodology:
Framatome, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," EMF-2328(P)(A)
Revision.O.
Evaluation Model PCT: 2057 °F (Reference 1)
Net PCT Effect Absolute PCT Effect Prior 10 CFR 50.46 Changes or Error Corrections - up -279°F 393 °F to Year 2023 (Reference 1)
Prior 10 CFR 50.46 Changes or Error Corrections - None None Year2024 New 10 CFR 50.46 Changes or Error Corrections -
Year2024
J Legacy error in homologous pump curve 0°F 0°F Sum of 10 CFR 50.46 Changes or Error Corrections -279°F 393 °F
The sum of the PCT from the most recent analysis using an acceptable evaluation model and the 1778 °F < 2200 °F estimates of PCT impact for changes and errors identified since this analysis
Legacy error in Reactor Coolant Pump (RCP) homologous curves.
A legacy error was identified in analytical inputs for the RCP homologous curves. The erroneous input error was evaluated by Framatome. The error has a negligible impact on the results of SBLOCA analysis, leading to an estimated peak cladding temperature (PCT) impact of O 0 F.
Reference:
- 1. Letter from S. Catron to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," L-2024-011, March 13, 2024 [ML24073A190].