L-2021-074, Submittal of Periodic Reports
| ML21118A029 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/14/2021 |
| From: | Coffey R Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2021-074 | |
| Download: ML21118A029 (2) | |
Text
April 14, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re:
Florida Power & Light Company Turkey Point Units 6 and 7 Docket Nos.52-040 and 52-041 Submission of Periodic Reports
References:
L-2021-074 10 CFR52.3 10 CFR 50.59 10 CFR 52.97(c) 10 CFR 50.46(a)(3) 10 CFR 52 Appendix D, X.B
- 1. FPL Letter L-2020-137 to NRC Dated October 14, 2020, Submission of Periodic Reports (ADAMS Accession No.11L20297A482)
- 2. FPL Letter L-2020-065 to NRC Dated April 9, 2020, Submission of Periodic Reports (ADAMS Accession No. 11L20108F588)
- 3. FPL Letter L-2019-074 to NRC Dated April 9, 2019, License Conditions 2D.(11) Schedules
- Initial Submittal*
- 4. Westinghouse Electric Company Letter DCP _NRC_003344 to the NRC dated March 24, 2021 - 10 CFR 50.46 Annual Report for the AP1000 Plant Design (ADAMS Accession No.11L21090A035)
The purpose of this letter is to submit periodic reports for Turkey Point Units 6 & 7 (PTN 6 & 7) as required by NRC regulations and/ or license conditions as a Part 52 combined license (COL) holder.
The following reports are addressed by this letter, updated from the previous reporting period (References 1 and 2):
- Semi-Annual Departures Report
- Semi-Annual Changes, Tests, and Experiments Report
- Semi-Annual Updat~ of the Operational Programs Implementation Schedule
- Annual 10 CFR 50.46 Report Florida Power & Light Company 15430 Endeavor Dave,Juptter, FL 33478
Turkey Point Units 6 and 7 Docket Nos.52-040 and 52-041 L-2021-074 Page 2 of 2 Semi-Annual Departures Report and Semi-Annual Changes, Tests, and Experiments Report
- For P1N 6 & 7, in accordance with the requirements of 10 CPR 50.59(d)(2) and 10 CPR 52, Appendix D, paragraphs X.B.1 and X.B.3.b, during the period October 1, 2020 through March 31, 2021:
- No changes, tests or experiments were implemented pursuant to 10 CPR 50.59(c).
- No plant-specific departures were implemented under 10 CPR 52, Appendix D,Section VIII.
Semi-Annual Update of the Operational Programs Implementation Schedule - Pursuant to the P1N 6 & 7 COLs Section 2.D.(11), the schedule for implementation of operational programs is to be updated every six months. Because there are no changes to FPL's construction decision, the schedule provided in Reference 3 is reaffirmed.
Annual 10 CPR 50.46 Report - The PTN 6 & 7 COLs incorporate by reference AP1000 Design Certification Document (DCD) Revision 19, and thus also the peak fuel cladding temperature calculations performed by Westinghouse Electric Corporation (WEq. Accordingly, the WEC 2020 Model Year 10 CPR 50.46 annual report for the AP1000 Design Certification Analysis of Record (AOR) applies to P1N 6 & 7 (Reference 4).
As described in the Reference 4 letter, there are no new emergency core cooling system model changes that impact peak cladding temperature (PCT) for the 2020 model year. The estimated PCT for the limiting transient, the Best Estimate Large Break Loss-of-Coolant Accident, remains at 2010°F and does not exceed the 10 CPR 50.46(b)(1) acceptance criterion of 2200°F. The summary of the AP1000 Design Certification AOR PCT margin allocations and their bases is provided in of the Reference 4 letter.
If you have any questions, or need additional information, please contact me at 561-304-6200.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April 14, 2021.
Sincerely,
~
Vice President Nuclear Florida Power & Light Company cc: USNRC Regional Administrator, Region II USNRC P1N 6 & 7 Project Manager, NRR/DNRL USNRC Senior Resident Inspector, Turkey Point Nuclear Plant