L-2016-146, Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications: Difference between revisions

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ENCLOSURE TO L-2016-146
ENCLOSURE TO L-2016-146
          ,,
     ,,,. Enclosure I-'"'    Page 1 of 1 Seabrook SBLOCA and LBLOCA PCTs Peak Clad                    Cumulative Temperature                      Change LBLOCA 2014 10 CFR 50.46 Annual Report <1l                        1939 &deg;F                        155 &deg;F Errors in 2015 <2l                                            0 &deg;F                          0 &deg;F Modeling errors in the lower support plate core barrel, and vessel cladding unheated conductors.
     ,,,. Enclosure I-'"'    Page 1 of 1 Seabrook SBLOCA and LBLOCA PCTs Peak Clad                    Cumulative Temperature                      Change LBLOCA 2014 10 CFR 50.46 Annual Report <1l                        1939 &deg;F                        155 &deg;F Errors in 2015 <2l                                            0 &deg;F                          0 &deg;F Modeling errors in the lower support plate core barrel, and vessel cladding unheated conductors.
2015 10 CFR 50.46 Annual Report                          1939 &deg;F                        155 &deg;F SBLOCA 2014 10 CFR 50.46 Annual Report <1l                      1373 &deg;F                          0 &deg;F No Errors in 2015 2015 10 CFR 50.46 Annual Report                          1373 &deg;F                          0 &deg;F References
2015 10 CFR 50.46 Annual Report                          1939 &deg;F                        155 &deg;F SBLOCA 2014 10 CFR 50.46 Annual Report <1l                      1373 &deg;F                          0 &deg;F No Errors in 2015 2015 10 CFR 50.46 Annual Report                          1373 &deg;F                          0 &deg;F References
: 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.
: 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.
: 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}}
ML15317A008, November 7, 2015}}

Revision as of 00:20, 5 February 2020

Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
ML16210A405
Person / Time
Site: Seabrook NextEra Energy icon.png
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)
v • d • e


Text

...~

NEXTeraT"'

ENERGYe L-2016-146 JUL 2 6 2016 10 CFR 50.46(a)(3)(ii)

Docket No. 50-443 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Seabrook Station 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 Peak Clad Cumulative Temperature Change LBLOCA 2014 10 CFR 50.46 Annual Report <1l 1939 °F 155 °F Errors in 2015 <2l 0 °F 0 °F Modeling errors in the lower support plate core barrel, and vessel cladding unheated conductors.

2015 10 CFR 50.46 Annual Report 1939 °F 155 °F SBLOCA 2014 10 CFR 50.46 Annual Report <1l 1373 °F 0 °F No Errors in 2015 2015 10 CFR 50.46 Annual Report 1373 °F 0 °F References

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
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