L-2016-146, Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
| ML16210A405 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/26/2016 |
| From: | Larry Nicholson NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2016-146 | |
| Download: ML16210A405 (3) | |
Text
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U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 JUL 2 6 2016 Seabrook Station NEXTeraT"'
ENERGYe L-2016-146 10 CFR 50.46(a)(3)(ii)
Docket No. 50-443 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications The purpose of this letter is to submit the 10 CFR 50.46 annual reporting information for NextEra Energy Seabrook, LLC.
Attached, please find the current Seabrook Station status including the results for years 2014 and 2015. Key references regarding this information are also provided in the attached.
There are no new commitments contained in the letter. Should you have any questions regarding_
this report, please contact Mr. Kevin J. Randall, Reactor Engineering Supervisor, at (603) 773-7992.
Sincerely, Laholson Director, Nuclear Licensing and Regulatory Compliance Enclosure cc:
D. Dorman, NRC Region I Administrator J. Lamb, NRC Project Manager, Project Directorate 1-2 P. Cataldo, NRC Senior Resident Inspector NextEra Energy, Inc. 700 Universe Boulevard, Juno Beach, FL 33408
ENCLOSURE TO L-2016-146
Enclosure I-'"'
Page 1 of 1 Seabrook SBLOCA and LBLOCA PCTs LBLOCA 2014 10 CFR 50.46 Annual Report <1l Errors in 2015 <2l Modeling errors in the lower support plate core barrel, and vessel cladding unheated conductors.
2015 10 CFR 50.46 Annual Report SBLOCA 2014 10 CFR 50.46 Annual Report <1l No Errors in 2015 2015 10 CFR 50.46 Annual Report Peak Clad Temperature 1939 °F 0 °F 1939 °F 1373 °F 1373 °F References Cumulative Change 155 °F 0 °F 155 °F 0 °F 0 °F
- 1.
Letter from M. Ossing to U. S. Nuclear Regulatory Commission, "Seabrook Station Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications," SBK-L-15140, Accession No. ML15194A041, July 9, 2015.
- 2.
Letter from M. Ossing to U. S. Nuclear Regulatory Commission, "Seabrook Station Best-Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report," SBK-L-15195, Accession No. ML15317A008, November 7, 2015