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Category:Annual Operating Report
MONTHYEARL-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2022-062, Annual Radiological Environmental Operating Report for Calendar Year 20212022-04-13013 April 2022 Annual Radiological Environmental Operating Report for Calendar Year 2021 L-2021-082, Submittal of 2020 Annual Environmental Operating Report2021-04-15015 April 2021 Submittal of 2020 Annual Environmental Operating Report L-2021-066, CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2021-04-14014 April 2021 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2020-044, Report of 10 CFR 50.59 Plant Changes2020-04-20020 April 2020 Report of 10 CFR 50.59 Plant Changes L-2020-068, 2019 Annual Environmental Operating Report2020-04-15015 April 2020 2019 Annual Environmental Operating Report L-2020-041, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2020-04-14014 April 2020 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2020-027, 2019 Annual Operating Report2020-01-12012 January 2020 2019 Annual Operating Report L-2019-044, Report of 10 CFR 50.59 Plant Changes2019-03-27027 March 2019 Report of 10 CFR 50.59 Plant Changes L-2019-057, Cf~ 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2019-03-19019 March 2019 Cf~ 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2019-039, 2018 Annual Operating Report2019-02-27027 February 2019 2018 Annual Operating Report L-2018-087, Transmittal of 2017 Annual Environmental Operating Report2018-04-10010 April 2018 Transmittal of 2017 Annual Environmental Operating 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-2018-051, 2017 Annual Operating Report2018-02-22022 February 2018 2017 Annual Operating Report L-2017-071, Submittal of Report of 10 CFR 50.59 Plant Changes, Tests and Experiments2017-05-0404 May 2017 Submittal of Report of 10 CFR 50.59 Plant Changes, Tests and Experiments L-2017-056, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report2017-03-27027 March 2017 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report L-2017-016, Transmittal of 2016 Annual Operating Report2017-02-0707 February 2017 Transmittal of 2016 Annual Operating Report L-2016-049, Annual Operating Report for St. Lucie 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors2016-03-0202 March 2016 Annual Operating Report for St. Lucie 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors L-2014-095, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2014-03-31031 March 2014 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2004-050, Cy 2003 Corrections to Annual Radioactive Effluent Release Report (L-2004-050 Dated February 27, 2004) Section 10. Process Control Program (PCP) Revisions, Page 6 and AP 0520025 Revision 13A with mark-up2014-02-27027 February 2014 Cy 2003 Corrections to Annual Radioactive Effluent Release Report (L-2004-050 Dated February 27, 2004) Section 10. Process Control Program (PCP) Revisions, Page 6 and AP 0520025 Revision 13A with mark-up L-2014-048, Annual Operating Report2014-02-12012 February 2014 Annual Operating Report L-2013-012, Annual Operating Report2013-01-0909 January 2013 Annual Operating Report L-2012-361, Report of 10 CFR 50.59 Plant Changes2012-10-0101 October 2012 Report of 10 CFR 50.59 Plant Changes L-2012-170, Annual Environmental Operating Report2012-04-24024 April 2012 Annual Environmental Operating Report L-2012-080, Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011, C-200, Offsite Dose Calculation Manual Revision 35.2012-03-0101 March 2012 Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011, C-200, Offsite Dose Calculation Manual Revision 35. ML12068A2072012-03-0101 March 2012 Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011 L-2012-073, 2011 Annual Operating Report2012-02-21021 February 2012 2011 Annual Operating Report L-2011-147, 2010 Annual Environmental Operating Report2011-04-20020 April 2011 2010 Annual Environmental Operating Report L-2011-116, Annual Radiological Environmental Operating Report for Calendar Year 20102011-04-19019 April 2011 Annual Radiological Environmental Operating Report for Calendar Year 2010 ML1109701462011-03-30030 March 2011 Units I and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2010-058, Annual Radiological Environmental Operating Report for Calendar Year 20092010-03-22022 March 2010 Annual Radiological Environmental Operating Report for Calendar Year 2009 ML1006106442010-02-25025 February 2010 St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 2009 L-2010-033, St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 20092010-02-25025 February 2010 St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 2009 L-2009-090, Annual Radiological Environmental Operating Report for Calendar Year 20082009-04-13013 April 2009 Annual Radiological Environmental Operating Report for Calendar Year 2008 L-2009-061, Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors2009-03-11011 March 2009 Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors L-2008-169, Amended Annual Radiological Environmental Operating Report for Calendar Year 20072008-07-28028 July 2008 Amended Annual Radiological Environmental Operating Report for Calendar Year 2007 L-2008-046, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2008-03-18018 March 2008 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2007-074, 2006 Annual Environmental Operating Report2007-04-25025 April 2007 2006 Annual Environmental Operating Report L-2007-021, Annual Operating Report2007-02-21021 February 2007 Annual Operating Report L-2006-263, Report of 10 CFR 50.59 Plant Changes During Period of February 15, 2005 Through June 12, 20062006-12-0505 December 2006 Report of 10 CFR 50.59 Plant Changes During Period of February 15, 2005 Through June 12, 2006 ML0612501642006-04-27027 April 2006 St. Lucie, Units 1 & 2 - 2005 Annual Environmental Operating Report L-2006-098, Annual Radiological Environmental Operating Report for Calendar Year 20052006-04-18018 April 2006 Annual Radiological Environmental Operating Report for Calendar Year 2005 L-2005-095, Annual Environmental Operating Report2005-04-26026 April 2005 Annual Environmental Operating Report L-2005-069, Annual Radiological Environmental Operating Report for Calendar Year 20042005-03-31031 March 2005 Annual Radiological Environmental Operating Report for Calendar Year 2004 L-2005-038, 2004 Annual Radioactive Effluent Release Report2005-02-28028 February 2005 2004 Annual Radioactive Effluent Release Report L-2005-037, Letter Transmitting, St. Lucie Units 1 and 2, 2004 Annual Overating Report2005-02-28028 February 2005 Letter Transmitting, St. Lucie Units 1 and 2, 2004 Annual Overating Report L-2004-081, Annual Radiological Environmental Operating Report2004-04-13013 April 2004 Annual Radiological Environmental Operating Report L-2004-070, Annual Environmental Operating Report2004-04-13013 April 2004 Annual Environmental Operating Report L-2004-012, Transmittal of the 2003 Annual Operating Report2004-02-12012 February 2004 Transmittal of the 2003 Annual Operating Report 2023-09-20
[Table view] Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 MAY 0 4 2017 Report of 10 CFR 50.59 Plant Changes L-2017-071 10 CFR 50.59(d) Pursuant to 10 CFR 50.59(d)(2), the attached report contains a brief description of any changes, tests and experiments, including a summary evaluation of each, which were made on Unit 1 during the period of Amendment No. 28 (April 25, 2015 through November 9, 2016) dated May 2017 and minor update 27A dated January 2016. This submittal correlates with the information included in Amendment 28 of the Updated Final Safety Analysis Report to be submitted under separate cover. Please contact us if there any questions on this information.
Licensing Manager St. Lucie Plant MJS/lrb Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Plant USNRC Senior Resident Inspector, St. Lucie Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 St. Lucie Unit 1 Docket No. 50-335 ST. LUCIE UNIT 1 DOCKET NUMBER 50-335 CHANGES, TESTS AND EXPERIMENTS MADE AS ALLOWED BY 10 CFR 50.59 FOR THE PERIOD OF APRIL 25, 2015 THROUGH NOVEMBER 9, 2016 AND MINOR UPDATE 27A DATED JANUARY 2016 (15 PAGES INCLUDING COVER) 1 L-2017-071 Enclosure St. Lucie Unit 1 Docket No. 50-335 INTRODUCTION This report is submitted in accordance with 10 CFR 50.59 (d)(2),which requires that: i) changes in the facility as described in the SAR; ii) changes in procedures as described in the SAR; and iii) tests and experiments not described in the SAR L-2017-071 Enclosure that are conducted without prior Commission approval be reported to the Commission in accordance with 10 CFR 50.90 and 50.4. This report is intended to meet these requirements for the period of April 25, 20t5 through November 9, 2016. This report is typically divided into three (3) sections.
First, changes to the facility as described in the Updated Final Safety Analysis-Report (UFSAR) performed by a Permanent Modification are addressed.
Second, changes to the facility/procedures as described in the UFSAR, or tests/experiments not described in the UFSAR, which are not performed by a Permanent Modification, are addressed.
Third, a summary of any Fuel Reload 10 CFR 50.59 evaluation is addressed.
Sections 1, 2 and 3 summarize specific 10 CFR 50.59 evaluations that evaluated the specific change(s).
Each of these 10 CFR 50.59 evaluations concluded that the change does not require a change to the plant technical specifications, and prior NRC approval is not required.
2 St. Lucie Unit 1 Docket No. 50-335 SECTION! EC 283007, R2 SECTION2 EC 284358, R1 EC 284437, R1 EC 287794, R2 SECTION3 EC 285570, R2 L-2017-071 Enclosure TABLE OF CONTENTS PERMANENT MODIFICATIONS PAGE PERMANENT REMOVAL OF ST. LUCIE UNIT 1 RCP 5 1B2 WHIP (CABLE) RESTRAINTS 10 CFR 50.59 EVALUATIONS INCREASED STEAM GENERATOR BLOWDOWN 9 FLOW RATE (UNIT 1) EVALUATION OF ACTIONS REQUIRED TO MITIGATE HOT LEG INJECTION SINGLE FAILURE VULNERABILITY 10 CONNECTION OF TEMPORARY AIR COMPRESSORS TO 11 SUPPORT UNIT 1 INSTRUMENT AIR COMPRESSOR REPLACEMENT FUEL RELOAD EVALUATIONS ST. LUCIE UNIT 1 CYCLE 27 RELOAD
- 14 3 St. Lucie TJnit 1 Docket No. 50-335 SECTION1 PLANT CHANGE / MODIFICATIONS 4 L-2017-071 Enclosure St. Lucie Unit 1 Docket No. 50-335
SUMMARY
EC 283007, R2 Permanent Removal of St. Lucie Unit 1 RCP 1B2 Whip (Cable) Restraints L-2017-071 Enclosure To allow for future maintenance of the reactor coolant pump, the upper RCP cable (whip) restraints were permanently removed. Regulatory Background The St. Lucie Unit 1 Construction Permit was issued on July 1, 1970 and an Operating Licensing was licensed in March 1976. Prior to 1986, General Design Criterion (GDC) 4, "Environmental and Missile Design Bases," required that systems and components important to safety be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharge fluids, which may result in equipment failures.
In accordance with NRC Branch Technical Position ASB 3-1, plants for which construction permits were tendered before July 1, 1993, and operating licenses were issued after July 1, 1975, should follow the guidance of Appendix B of ASB 3-1 by A Giambusso, December 1972, General Information Required for Consideration of the Effects of a Piping System Break Outside Containment")
and also provide moderate energy piping failure analyses in accordance with Branch Technical Position ASB 3-1. Accordingly, the original St. Lucie Unit 1 design bases considered all dynamic effects (missile generation, pipe whipping, pipe break reaction forces, jet impingement forces, compartment, sub-compartment and cavity pressurizations and decompression waves with the ruptured pipe) and all environmental effects (pressure, temperature, humidity, and flooding) resulting from arbitrary intermediate pipe ruptures.
Circa 1986, GDC 4 was revised to read: "Environmental and dynamic effects design bases". Structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing; and postulated accidents, including loss-of-coolant accident.
These structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit. However, dynamic effects associated with postulated pipe ruptures in nuclear power units may be excluded from the design basis when analyses reviewed and approved by the Commission demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping." Consistent with the revision to GDC 4, on June 19, 1987, the NRC issued Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements which finalized a revision to Branch Technical Position (BTP) MEB 3-1 of Standard Review Plan (SRP) Section 3.6.2 in NUREG-0800.
The revisions to BTP MEB 3-1 and SRP 3.6.2 eliminated all dynamic effects and all environmental effects resulting from arbitrary intermediate pipe ruptures.
This action allows the elimination of pipe whip restraints and jet impingement shields placed to mitigate the effects of arbitrary intermediate pipe ruptures, and other related changes. On October 30, 1990, the NRC accepted Topical Report CEN-367, "Leak-Before-Break Evaluation of Primary Loop Piping in Combustion Engineering Designed Nuclear Steam Supply Systems, which was submitted for staff review by Combustion Engineering Owners Group (CEOG) letter dated November 20, 1987. FPL was a participating CEOG member and St. Lucie Units 1 and 2 were included in the bounding analyses submitted.
i 5
St. Lucie Unit 1 I>ocketN"o.
50-335 L-2017-071 Enclosure By letter to the N"RC dated August 26, 1992, FPL proposed to eliminate the dynamic effects associated with high energy pipe rupture in the reactor coolant system piping from the licensing and design bases of St. Lucie Units 1 and 2 by the application of leak-before-break (LBB) technology.
This change to the licensing and design bases is permitted by revised GI>C-4 of Appendix A to 10 CPR 50. By N"RC letter dated March 5, 1993, the staff concluded that since the St. Lucie Units are bounded by the CEOG analyses and the leakage detection systems are capable of detecting the specified leakage rate, the dynamic effects associated with postulated pipe breaks in the primary coolant system piping can be excluded from the licensing and design bases of the St. Lucie Units. Furthermore by N"RC letter dated July 9, 2012, N"RC staff concludes that Leak Before Break remains valid for SL-1 under EPU conditions.
TI1e Unit 1 UFSAR was updated to incorporate the effects of the staff's approval.
Section 3.1.4 was revised to read: I>ue to the application of leak before break methodology to the RCS hot and cold leg piping, the dynamic effects of a loss of coolant accident do not have to be considered.
A technical evaluation was performed to demonstrate that the probability or likelihood of large pipe breaks occurring in the primary coolant loops is sufficiently low that tl1ey need not be a design basis (see Reference 24 in Section 3.6) UFSAR Section 3.6.2 was revised to include the following acceptance criteria:
It should be noted that circumferential (guillotine) and longitudinal (slot) breaks in RCS hot and cold leg piping are no longer considered a design basis for GI>C 4 (Reference 27 N"RC acceptance letter for before-break).
The primary loop piping is not susceptible to failure from the effects of corrosion, water hammer, fatigue, brittle fracture or indirect causes such as missiles or failure of nearby components.
As a result, the mechanical/
structural loadings associated with the dynamic effects of a large hot or cold leg break need not be considered.
The proposed permanent removal of the upper two 3.5-inch reactor coolant pump RCP 1B2 whip (cable) restraints meets the acceptance criteria found in Generic Letter 87-11. Also as documented in N"RC letter dated March 5, 1993, the N"RC staff has concluded that since the St. Lucie Units are bounded by the CEOG analyses and the leakage detection systems are capable of detecting the specified leakage rate, the dynamic effects associated with postulated pipe breaks in tl1e primary coolant system piping can be excluded from the licensing and design bases of the St. Lucie Units. The EPU leak-before-break evaluation is based on evaluation CEN"-367-A.
The primary loop piping normal operating, SSE and pressure loads due to the EPU conditions were used in the EPU evaluation.
The results of the evaluation demonstrated that break recommended margins for the primary loop piping continue to be satisfied for the EPU conditions.
Calculation CN"-MRCI>A-09-68 provides an analysis of the RCP and surrounding components to demonstrate the RCP HELB cable restraints for pumps 1Al, 1A2, 1Bl and 1B2 can be permanently removed. In addition, calculation CN"-MRCI>A-09-06 documents tl1at sufficient leak-before-break margin on crack stability is maintained on the main coolant loop hot and cold leg pipes under EPU conditions.
N"RC letter dated July 9, 2012, concludes that Leak Before Break remains valid for SL-1 under EPU conditions.
The permanent removal of the upper RCP 1B2 whip restraints meets the acceptance criteria of BTP 3-1, as contained in SRP Section 3.6.2, in that absent the whip restraints the primary coolant system piping continues to meet the applicable ASME Code design requirements.
Evaluation There are no Technical Specifications that address the restraints.
However, as discussed in the Safety Evaluation by the N"RC on Leak-Before-Break (LBB) Technology, the acceptance of LBB is based on a leakage detection system consistent witl1 Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage I>etection Systems." Technical Specification Section 3/4.4.6.1 addresses the RCS leakage detection 6
St. Lucie Unit 1 Docket No. 50-335 .L-2017-071 Enclosure system and no changes to this section or any other section is required as a result of the removal of the cable restraints.
A License Amendment Request is not required.
The RCS whip restraints were installed during initial construction of St. Lucie Unit 1 to mitigate the dynamic effects associated with postulated RCS hot and cold leg piping breaks. In 1993 the dynamic effects associated with postulated pipe ruptures in RCS hot and cold leg piping were excluded from the design and licensing bases of St. Lucie Unit 1, as described in UFSAR Section 3.6. In 2012, it was concluded that the leak before break analysis remains valid for EPU conditions.
Because the proposed change does not require a change to the technical specifications and does not meet any of the criteria in 10 CFR 50.59(c)(2), the change can be made without obtaining a license amendment pursuant to 10 CFR 50.90. 7 St. Lucie Unit 1 Docket No. 50-335 SECTION2 50.59 EVALUATIONS 8 L-2017-071 Enclosure
Lucie Unit 1 Docket No. 50-335 SUIY.Ilv1ARY EC 284358, Rl Increased Steam Generator Blowdown Flow Rate (Unit 1) L-2017-071 Enclosure The EC 284358 associated with this 50.59 Evaluation was prepared to increase the current steam generator blowdown (SGBD) system flow rate values in the accident analysis from 50 gpm or 65 gpm per SG to a maximum value of 120 gpm per SG, and make the necessary UFSAR changes as a result. The analyses also assumed new times for SGBD manual isolation in the events at 25 minutes, instead of current timing documented in the UFSAR for the Station Blackout and Chapter 10 Loss of Feedwater event. The SG low level RPS trip setpoints have also been changed in the analyses to remove some existing conservatism.
There are no physical changes to plant systems or components from this EC, and documentation changes are necessary to address concerns first identified in ARs 02030177 and 02031217.
The activity has been considered to be adverse per 50.59 screening, since it affects the maximum SGBD flow rate assumed in the accident analyses for the loss of feedwater (LOF) events (Chapter 10 and 15), feedwater line break (FLB) event, and Station Blackout (SBO) event, and operator action time requirements have been changed. Reanalysis calculations for these events used as input in this evaluation were provided to FPL via AREVA letter FAB15-00438, "St. Lucie-1 Evaluation of Increased Steam Generator Blowdown Flow", dated 07-16-2015. This evaluation is applicable to the UFSAR changes (EC Attachment
- 5), applicable to procedure changes (as described in Section 2.3 of the EC and any other related), and Operator Action Times evaluation PSL-ENG-SEMS-12-006 changes. Because the proposed change does not require a change to the technical specifications and does not meet any of the criteria in 10 CPR 50.59(c)(2), the change can be made without obtaining a license amendment pursuant to 10 CPR 50.90. 9 St. Lucie Unit 1 Docket No. 50-335 SUJ\WARY EC 284437, Rl Evaluation of Actions Required to :Mitigate Hot Leg Injection Single Failure Vulnerability L-2017-071 Enclosure The St. Lucie Unit 1 FSAR was recently updated to include a description of measures required for the mitigation of Hot Leg Injection single failure vulnerability.
In conjunction with this update, 1-EOP-99 was revised and new procedures 1-G11E-100.03 and 1-G11E-100.03A were issued. These changes were all "screened out" under a 10 CFR 50.59 screening.
In July 2015, AR 2063184 was initiated to document the following: "The NRC senior resident inspector commented on the 50.59 screenings associated with the procedures and UFSAR changes that were made to formalize the use of jumpers for certain Unit 1 alternate Hot Leg Injection failure scenarios.
NEI guidance for 50.59s typically expects that evaluations for the use of manual actions in lieu of automatic actions would 'screen in' with respect to performing a full 50.59 evaluation." Engineering Evaluation PSL-ENG-SENS-15-001, under EC 284437, evaluates the FSAR change, issues a new UFSAR change request (UCR), and evaluates the changes that were made to the procedures.
This Evaluation applies to the new UCR, and to the previous UFSAR change and the procedures changes, retroactively.
Because the proposed change does not require a change to the technical specifications and does not meet any of the criteria in 10 CFR 50.59(c)(2), the change can be made without obtaining a license amendment pursuant to 10 CFR 50.90. 10 St. Lucie Unit 1 Docket No. 50-335 SU:MI\1ARY EC 287794, R2 Connection of Temporary Air Compressors to Support Unit 1 Instrument Air Compressor Replacement L-2017-071 Enclosure EC 287794 provides Temporary Air Compressors and Dryers (TAC/Ds) to supply compressed air to the Instrument Air System (IAS) while the existing air compressors and dryers are being replaced under EC# 283796. EC 283796 replaces the existing Instrument Air Compressors (IA COJ\1PR 1A, IA COJ\1PR 1B, IA COJ\1PR 1C, IA COJ\1PR 1D), Air Dryers (IA DYR 1A and IA DYR 1B) and associated equipment.
The sequence of activities requires disconnecting and removing all of the existing compressors before the new compressors and equipment can be installed.
From the time the existing compressors are disconnected until the new compressors and equipment are turned over to operations, instrument air will be supplied by three, redundant, > 200% capacity, temporary compressors and dryers via temporary rubber hoses. One electrically driven compressor, two diesel driven compressors, and three dryers will be installed.
Each compressor and dryer is capable of supplying air at > 200% of the existing 100% air compressors.
If the electrically driven compressor trips off line, one of the two redundant diesel driven compressors will start automatically to supply compressed air to the IAS. If that diesel driven compressor fails to supply the required air, the other diesel driven compressor will automatically start. Both diesel driven compressors have a nominal 8-hour fuel supply. Temporary rubber air hoses will be run to complete the connection from the temporary air dryers to the instrument air system. The Unit 1 to Unit 2 cross tie is unchanged.
The TAC/Ds have enough capacity to supply the instrument air needs for both Units if necessary.
Thus cross tie capabilities are unaffected.
Instrument air controls and setpoints are unchanged.
All compressors are controlled locally. The TAC/Ds must provide air of the same quality, and as reliably as the permanent compressors and dryers to avoid placing the plant in an unstable condition, and/ or requiring a reactor scram per procedure 1-AOP-18.01, Step 4.1.1. Per Procedure EN-AA-203-1201, Section 4.5.8, a change is to be considered adverse if it decreases the reliability of the design function, or reduces the existing redundancy, diversity, or defense in depth. It is conservatively assumed that the use temporary rubber hose connections are not as reliable as permanently installed equipment and this is evaluated here-in. The use of a temporary air supply compressors for the IAS does not affect and is not affected by the Technical Specifications.
Using temporary compressors and dryers to provide air to the IAS has a less tl1an minimal effect on the IAS reliability, and no effect on the consequences of a loss of instrument air. Because the proposed change does not require a change to the technical specifications and does not meet any of the criteria in 10 CFR 50.59(c)(2), the change can be made without obtaining a license amendment pursuant to 10 CFR 50.90. 11 St. Lucie Unit 1 Docket No. 50-335 SECTION3 CORE RELOAD EVALUATION 12 L-2017-071 Enclosure St. Lucie Unit 1 Docket No.
SU:MJ\1ARY EC 285570, R2 St. Lucie Unit 1 Cycle 27 Core Reload L-2017-071 Enclosure St. Lucie Unit 1 Cycle 27 Core Reload did not require a 10 CFR 50.59 Evaluation.
The discussions within this EC, along with the 10 CFR 50.59 Applicability
/Screening which were performed, justify that the design and operation of the Cycle 27 reload core does not meet any of the criteria in 10 CFR 50.59(c)(2).
The core reload activities can be implemented with no changes to the St. Lucie Unit 1 Technical Specifications.
The safety analyses results are within the current design basis, within the acceptance limits provided by the NRC regulatory criteria and within the criteria provided by 10 CFR 50.59. Therefore, prior NRC approval is not required for implementation of this EC. 13