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Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-058, CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-03-25025 March 2019
CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report
L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018
CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications
L-2017-102, Submittal of 10 CFR 50.46 - Emergency Core Cooling 30-Day Report2017-06-0202 June 2017
Submittal of 10 CFR 50.46 - Emergency Core Cooling 30-Day Report
L-2017-069, Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction2017-04-17017 April 2017
Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction
NRC-2017-0012, Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result2017-02-24024 February 2017
Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result
L-2016-124, 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach2016-06-17017 June 2016
10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach
NRC 2016-0015, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2016-04-0606 April 2016
Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report
L-2016-065, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, - 30 Day Special Report2016-04-0505 April 2016
Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, - 30 Day Special Report
NRC 2014-0086, 10 CFR 50.46 30-Day Report2014-12-11011 December 2014
10 CFR 50.46 30-Day Report
L-2014-359, 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, 30 Day Special Report2014-12-0303 December 2014
10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors, 30 Day Special Report
NRC 2014-0029, CFR 50.46 Annual Report/30-Day Report2014-04-18018 April 2014
CFR 50.46 Annual Report/30-Day Report
SBK-L-14073, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report2014-04-16016 April 2014
Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report
L-2014-077, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report2014-03-24024 March 2014
CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report
L-2014-065, Special Report - Accident Monitoring Instrumentation2014-02-25025 February 2014
Special Report - Accident Monitoring Instrumentation
L-2014-037, Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report2014-02-18018 February 2014
Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report
NRC 2014-0012, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2014-02-13013 February 2014
Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report
NRC 2013-0081, Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report2013-08-23023 August 2013
Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report
L-2013-184, Special Report - Accident Monitoring Instrumentation2013-05-30030 May 2013
Special Report - Accident Monitoring Instrumentation
L-2013-117, Special Report - Accident Monitoring Instrumentation2013-03-29029 March 2013
Special Report - Accident Monitoring Instrumentation
SBK-L-12264, Nuclear Fuel Pellet Thermal Conductivity Degradation Impact on Current Seabrook Be LBLOCA Analysis Using the 1996 Cqd Methodology 10 CFR 50.46 30-Day Report2012-12-21021 December 2012
Nuclear Fuel Pellet Thermal Conductivity Degradation Impact on Current Seabrook Be LBLOCA Analysis Using the 1996 Cqd Methodology 10 CFR 50.46 30-Day Report
NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum2012-05-30030 May 2012
ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum
SBK-L-11141, Submittal of Special Report Regarding Containment Enclosure Building Structural Integrity2011-07-11011 July 2011
Submittal of Special Report Regarding Containment Enclosure Building Structural Integrity
L-2010-235, LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable2010-10-13013 October 2010
LER, Turkey Point, Units 3 and 4, Special Report - Accident Monitoring Instrumentation Inoperable
L-2010-114, Special Report Re Inoperable Main Steam Lines High Range-Noble Gas Effluent Monitor Greater than 7 Days2010-06-14014 June 2010
Special Report Re Inoperable Main Steam Lines High Range-Noble Gas Effluent Monitor Greater than 7 Days
L-2010-100, Accident Monitoring Instrumentation Special Report2010-05-14014 May 2010
Accident Monitoring Instrumentation Special Report
NRC-2007-0055, Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.462007-07-0303 July 2007
Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.46
L-2005-096, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report and 30-Day Report2005-04-27027 April 2005
CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - Annual Report and 30-Day Report
ML0508303282004-05-0606 May 2004
Event Notification 40728 for Point Beach
NRC 2003-0042, Reporting of Fire Barriers Degraded for More than Seven Days2003-05-0909 May 2003
Reporting of Fire Barriers Degraded for More than Seven Days
NRC 2002-0095, Reporting of Fire Barriers Degraded for More than Seven Days2002-10-22022 October 2002
Reporting of Fire Barriers Degraded for More than Seven Days
NRC 2002-0083, Reporting of Fire Barriers Degraded for More than Seven Days2002-09-26026 September 2002
Reporting of Fire Barriers Degraded for More than Seven Days
ML0307702772002-08-0707 August 2002
2-page Abnormal Occurrence Writeup for 11/29/2001 Event Potential Loss of All Auxiliary Feedwater at Point Beach Plant
ML18227A5071977-07-29029 July 1977
Transmittal of Licensee Event Report 251-77-4, Steam Generator Tube Plugs
ML18227A5081977-05-13013 May 1977
Transmittal of Licensee Event Report 251-77-2 Boric Acid Transfer Pumps
2019-03-25
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June 17, 2016 L-2016-124 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: Florida Power & Light Company Turkey Point Units 3 and 4 Docket Nos. 50-250, 50-251 NextEra Energy Seabrook, LLC Seabrook Station Docket No. 50-443 NextEra Energy Point Beach, LLC Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266, 50-301
Subject:
10 CFR 50.46 30-Day Report
References:
- 1. FPL letter to NRC, dated April 5, 2016, "Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors" - 30 Day Special Report"
- 2. NextEra Energy Seabrook Station, LLC letter to NRC, November 7, 2015, "Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report"
- 3. NextEra Energy Point Beach, LLC letter to NRC, dated April 6, 2016, "Large Break Loss-of-Coolant Accident Margin Summary Sheet Day Report" In accordance with 10 CFR 50.46(a)(3)(ii), Florida Power & Light's Turkey Point Nuclear Plant, NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC (hereby referred to as NextEra), are submitting this 30-day report for the Turkey Point Nuclear Plant (PTN), Units 3 and 4, Seabrook Station (SBK), and Point Beach Nuclear Plant (PBNP), Units 1 and 2 for the emergency core cooling system (ECCS) analysis performed by Westinghouse Electric Company, LLC.
NextEra Energy, Inc. 700 Universe Boulevard, Juno Beach, FL 33408
""'-' .. L~016-124 Page 2 of 2 NextEra has been informed by Westinghouse of a closely-related group of errors related to the calculation of high temperature oxidation in the Point Beach Units 1 and 2, Seabrook and Turkey Point Units 3 and 4 Best-Estimate (BE) Large-Break Loos-of-Coolant Accident analyses. Previous LBLOCA changes to peak clad temperature (PCT) are documented in Reference 1, 2 and 3 for each site, respectively. NextEra has determined that correcting the high temperature oxidation calculation in WCOBRA!TRAC is estimated to have a negligible impact on the BE LBLOCA PCT analysis results, leading to an estimated PCT impact of 0°F. This results in the PCT limit of 2200 °F continuing to be met.
Additionally, NextEra determined that after correcting the high temperature oxidation calculation in WCOBRA!TRAC, the BE LBLOCA analysis results continued to maintain compliance with the 10 CFR 50.46 criteria including maximum local oxidation and core wide oxidation criteria.
Although there is no change to the PCT, this information is being submitted within 30 days, pursuant to 10 CFR 50.46, since Turkey Point, Seabrook and Point Beach already reside above a cumulative change of 50 °F (which constitutes a "significant change" per the 10 CFR 50.46 regulation).
This submittal contains no new commitments or revisions to existing commitments.
S~ely1tL Larry Nicholson Director, Nuclear Licensing and Regulatory Compliance cc: Administrator, Region I, USNRC Administrator, Region II, USNRC Administrator, Region Ill, USNRC Project Manager, Turkey Point Nuclear Plant, USNRC Project Manager, Seabrook Station, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Turkey Point Nuclear Plant, USNRC Resident Inspector, Seabrook Station, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC
