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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