L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report
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| ML15083A264 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/10/2015 |
| From: | Costanzo C R Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15083A306 | List:
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| References | |
| L-2015-048 | |
| Download: ML15083A264 (3) | |
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List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants L-2010-059, Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water2010-03-18018 March 2010 Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water ML1008304422010-03-18018 March 2010 Florida Dept of Environmental Protection - Wastewater Application Form 2CS - Permit to Discharge Process Wastewater from New or Existing Industrial Wastewater Facilities to Surface Water L-2009-101, Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 20082009-04-22022 April 2009 Report of 10 CFR 50.59 Plant Changes, for the Period of May 28, 2007 Through November 21, 2008 L-2008-261, Technical Specification Special Report Inoperable Containment Sump Wide Range Level Channel B2008-12-16016 December 2008 Technical Specification Special Report Inoperable Containment Sump Wide Range Level Channel B ML0807010172008-03-10010 March 2008 EPRI Reports (St. Lucie Pressurizer Nozzle DM Weld Examination Project Internal Office Report) L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)2007-11-0707 November 2007 Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) L-2007-167, Report of 10 CFR 50.59 Plant Changes During the Period of December 19, 2005 Through May 27, 20072007-10-29029 October 2007 Report of 10 CFR 50.59 Plant Changes During the Period of December 19, 2005 Through May 27, 2007 L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42007-10-29029 October 2007 Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2007-137, Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B2007-08-31031 August 2007 Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B L-2007-029, Semi-Annual Fitness-For-Duty Program Performance Data for the Six-Month Period Ending December 31, 20062007-02-26026 February 2007 Semi-Annual Fitness-For-Duty Program Performance Data for the Six-Month Period Ending December 31, 2006 L-2007-020, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20062007-02-0606 February 2007 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2006 L-2006-078, Proposed License Amendment, Containment Spray Nozzle Surveillance Change2006-10-19019 October 2006 Proposed License Amendment, Containment Spray Nozzle Surveillance Change L-2006-217, Day Post Outage Steam Generator Report Technical Specification 4.4.5.5.c2006-09-20020 September 2006 Day Post Outage Steam Generator Report Technical Specification 4.4.5.5.c L-2006-152, NRC Order EA-03-009 - 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Out of Service2006-02-22022 February 2006 Technical Specification Special Report, Radwaste Building Exhaust System, Plant Ventilation Stack Particulate Iodine and Noble Gas (Sping) Radiation - Out of Service L-2006-043, Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions.2006-01-23023 January 2006 Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions. 2023-09-28 |
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March 10, 2015 L-2015-048 F=PL. 10 CFR 50.54(f)U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 RE: FPL/St. Lucie Plant's Flooding Hazards Reevaluation for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
References:
- 1) NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," dated March 12, 2012, Accession No. ML 12073A348.
- 2) NRC Letter, "Prioritization of Response Due Dates for Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," dated May 11, 2012, Accession No ML 12097A509.
- 3) FPL Letter dated June 11, 2012, FPL/St. Lucie Plant's 90 Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendations 2.1 and 2.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, Accession No ML 12172A 143.On March 12, 2012, the NRC issued the Reference 1 letter to all power reactor licensees and holders of construction permits in active or deferred status. Enclosures 2 and 4 of the Reference I letter contain specific Requested Actions, Requested Information, and Required Responses associated with Recommendations 2.1 and 2.3 for Flooding Evaluations and Walkdowns, respectively.
Reference 3 provided FPL's 90-day response to Reference 1 for the St. Lucie Plant.Reference 2 identified the response date of March 12, 2015 for the St. Lucie Plant's flood hazard reevaluation which corresponds to 3 years from the date of Reference
- 1. The attachment to this letter provides the flooding hazards reevaluation for the St. Lucie Plant. The flooding hazards reevaluation concluded an interim evaluation is required to determine the effects of Local Intense Precipitation (LIP) since this flood-cause mechanism is not bounded by the current plant design-bases flood hazard. Once the interim evaluation of LIP is completed, an interim measures known, additional correspondence will be submitted to the NRC prior to completion of the Integrated Assessment.
The Integrated Assessment report for St. Lucie will be submitted by March 12, 2017. A01 0 Florida Power & Light Company J6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2015-048 Page 2 This letter makes no new commitments or changes to any existing commitments.
If you have any questions or require additional information, please contact Eric Katzman, St.Lucie Licensing Manager, at (772) 467-7734.I declare under penalty of perjury that the foregoing is true and correct.Executed on March (0 , 2015 Respectfully submitted, Christopher R. Costanzo Site Vice President St. Lucie Plant CRC/KWF Attachment
-Flooding Hazards Reevaluation Report FPL-072-PR-002, Revision 0.cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Units 1 and 2 L-2015-048 Attachment I Flooding Hazards Reevaluation Report FPL-072-PR-002, Revision 0 Next 231 Pages