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Category:Annual Operating Report
MONTHYEARL-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report 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-2023-108, 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 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 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-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-2005-037, 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-2005-038, 2004 Annual Radioactive Effluent Release Report2005-02-28028 February 2005 2004 Annual Radioactive Effluent Release Report L-2004-070, Annual Environmental Operating Report2004-04-13013 April 2004 Annual Environmental Operating Report 2024-03-13
[Table view] Category:Letter type:L
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-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-2023-175, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule 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 2024-09-09
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II 0 FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 December'5, 2006 L-2006-263 10 CFR 50.59 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Unit 2 Docket No. 50-389 Report of 10 CFR 50.59 Plant Changes Pursuant to 10 CFR 50.59(d)(2), the attached report contains a brief description of any changes, tests, and experiments, including a summary of the 50.59 evaluation of each which were made on Unit 2 during the period of February 15, 2005 through June 12, 2006. This submittal correlates with the information included in Amendment 17 of the Updated Final Safety Analysis Report submitted under separate cover.Please contact us should there by any questions regarding this information.
Very truly yours, GLJ/tlt Attachment q7 an FPL Group company ST. LUCIE UNIT 2 DOCKET NUMBER 50-389 CHANGES, TESTS AND EXPERIMENTS MADE AS ALLOWED BY 10 CFR 50.59 FOR THE PERIOD OF FEBRUARY 15, 2005 THROUGH JUNE 12, 2006 1 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 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 February 15, 2005 through June 12, 2006.This report is divided into three (3) sections.
First, changes to the facility as described in the Updated Final Safety Analysis Report (UFSAR) performed by a Plant Change/Modification (PC/M). 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 PC/M. Third, a summary of any fuel reload 50.59 evaluation.
Each of the documents summarized in Sections 1,2 and 3 includes a 10 CFR 50.59 evaluation that evaluated the specific change(s).
Each of these 50.59 evaluations concluded that the change does not require a change to the plant technical specifications, and that prior NRC approval is not required.2 TABLE OF CONTENTS SECTION 1 PLANT CHANGE/MODIFICATIONS Feedwater Control Replacement
-Phase 2 PAGE 05034 5 SECTION 2 SENS-00-013 SECJ-04-064 SENS-06-038 SECTION 3 50.59 EVALUATIONS PAGE Use of PRC-01 Resin to Remove Co-58 Contaminants Cask Crane Main Hoist Weight Limit Increase to 150 Tons Fuel Handling Building Placement of Tri-Nuclear FilterNacuum Above Spent Fuel Racks for Spent Fuel Pool Cleanup RELOAD EVALUATION 7 8 9 PAGE 05197 St Lucie Unit 2 Cycle 16 Reload 11 3 SECTION 1 PLANT CHANGE / MODIFICATIONS 4
PLANT CHANGEIMODIFICATION 05034 REVISION 0 FEEDWATER CONTROL REPLACEMENT
-PHASE 2 Summary: This modification upgrades the existing Feedwater Regulating System (FWRS), Steam Bypass Control System (SBCS), and the Reactor Coolant Pump (RCP) monitoring and display system with new Distributed Control System (DCS) equipment and software.The new DCS equipment will interface with the installed DCS and Plant Data Network.A new version of software, version 8.0, has been developed and migrated over to the existing DCS to improve system performance.
This modification upgrades the ABB controllers FIC-9011/9021 located on Reactor Turbine Generator Board (RTGB) 202 with DCS compatible touch screen manual/auto (M/A) stations.
Ten RTGB 202 indicators and six RTGB 202 recorders associated with the Feedwater and sixty RCP indicators on RTGB 203 are being replaced with Flat Panel Displays (FPDs).A new cabinet (ALC-6) was installed in the cable spreading room. The cabinet houses a new control processor, field-bus modules, baseplates and power supplies to interface with the annunciator logic cabinets.The reason for this modification was to reduce the instability (oscillations) of the FWRS and to upgrade this control system along with the SBCS Steam Dump to Condenser Valve controls and the RCP monitoring and display system to a DCS. The existing Low Power Feedwater 15% Bypass Control Valves and SBCS Steam Dump to Condenser Valve pneumatic positioners were replaced with digital positioners to enhance tuning and diagnostic capability.
5 SECTION 2 50.59 EVALUATIONS 6
EVALUATION SENS-00-013 REVISION 4 USE OF PRC-01 RESIN TO REMOVE CO-58 CONTAMINANTS Summary: Revisions 0, 1 and 2 were identified in the 50.59 summary report issued in 2002.Revision 3 was identified in the 50.59 summary report issued in 2005. Revision 4 was approved in 2006 and is thus included in this report.This evaluation was prepared to examine the use of PRC-01 resin material in the chemical and volume control system (CVCS) letdown demineralizers without mode restrictions and extends authorized use to the Fuel Pool Ion Exchanger.
Revision 1 made minor modifications to the plant restrictions provided previously, to add and more precisely paraphrase UFSAR text and to include an additional required action related to calibration of the CVCS ion exchanger bypass valve.Revision 2 provided a basis for extending use of PRC-01 resin to any condition where the effective neutron multiplication factor is less than 1.0, consistent with the plant restrictions identified herein. Revision 2 also incorporated format and content changes necessary to comply with the changes to 10 CFR 50.59.Revision 3 removed a requirement that the PRC-01 resin must be taken out of service when hydrogen peroxide concentration in the RCS is greater than 5 ppm. This requirement was originally provided to conservatively reduce exposure of the resin to oxidizing environments.
Laboratory testing and subsequent plant experience indicates this restriction is not required when plant chemistry is maintained in accordance with EPRI guidelines.
Revision 3 also provided some minor administrative documentation changes.Revision 4 extends use of PRC-01 resin in the demineralizers in the CVCS letdown subsystem when the reactor is critical and extends authorized use of PRC-01 to the Fuel Pool Ion Exchanger.
The online restriction in CVCS use was initially provided as one of a number of restrictions governing the first use of PRC-01 resin at St. Lucie.Subsequent plant experience indicates this restriction is not required to maintain plant chemistry in accordance with EPRI guidelines.
Extension of PRC-01 use to the Fuel Pool Ion Exchanger will provide additional water clarity and is consistent with use at Turkey Point and other plants. In addition, a number of other more minor changes are made to align St. Lucie's more restrictive first-use procedure with current vendor guidance.7 EVALUATION SECJ-04-064 REVISIONS 0 & 1 CASK CRANE MAIN HOIST WEIGHT LIMIT INCREASE TO 150 TONS Summary: The cask handling cranes at St. Lucie Units 1 and 2 have been replaced with new single-failure-proof cask cranes of greater capacity.
The new cranes have a 150 ton single-failure-proof main hoist and a conventional 25 ton auxiliary hoist.The purposes of this evaluation are to increase the main hoist load limit to the maximum critical load capacity of the new main hoist (150 tons); expand the main hoist safe load path to include all the area that is accessible to the main hoist; and permit the main hoist to place the cask lid on the cask when the cask contains spent fuel.The main hoist load increase and expanded safe load path are not limited to spent fuel casks. Load transport safety does not depend on the load shape or composition.
Therefore, the main hoist may be used to transport other loads of up to 150 tons within the area accessible to the main hoist.For the purpose of this evaluation, placing the lid on the cask includes lowering the lid onto the cask and/or lifting the lid off the cask. (This recognizes the possibility that it may be desired to raise the lid after it has been set on the cask.)The main hoist load limit was increased by revising Unit 2 UFSAR Sections 9.1.4.1.2.2 and 13.7.1.8 through 13.7.1.8.2.
The main hoist load path was expanded by revising the heavy loads procedure, AP-0010438.
The main hoist permissive to place the cask lid on the cask when the cask contains spent fuel is provided by revising Unit 2 UFSAR Section 13.7.1.7.1 and the heavy loads procedure, AP-0010438.
Revision 1 incorporates updated references.
8 EVALUATION SENS-06-038 REVISIONS 0 & 1 FUEL HANDLING BUILDING PLACEMENT OF TRI-NUCLEAR FILTER/VACUUM ABOVE SPENT FUEL RACKS FOR SPENT FUEL POOL CLEAN-UP Summary: Water in the spent fuel pool (SFP) was exhibiting a high level of turbidity, a condition that will hinder the movement of fuel assemblies in the pool. To alleviate this condition a Tri-Nuclear filter/vacuum system was placed in the SFP to filter the pool water. The filter/vacuum equipment was attached to existing handrail support posts and suspended in the pool above the storage racks.Revision 1 was issued to add discussion regarding the potential for the filter/vacuum to drop and land flush on one or more spent fuel assemblies.
9 SECTION 3 RELOAD EVALUATION 10 PLANT CHANGE/MODIFICATION 05197 REVISIONS 0 ST. LUCIE UNIT 2 CYCLE 16 RELOAD Summary: This engineering package provides the reload core design for St. Lucie Unit 2 Cycle 16 developed by Florida Power & Light Company (FPL) and Westinghouse Electric -Combustion Engineering (W-CE). The Cycle 16 core was designed for a nominal cycle length of 11,240 EFPH, based on a nominal Cycle 15 length of 10,200 EFPH. The Cycle 16 reload design supports an additional end-of-cycle coastdown length of 360 EFPH with a maximum reduction in primary coolant inlet temperature to 535 degrees F.The primary design change to the core for Cycle 16 was the replacement of 77 irradiated fuel assemblies with 72 fresh Region T assemblies and 4 irradiated Region P fuel assemblies and 1 Region S assembly currently residing in the spent fuel pool. The fuel in the Cycle 16 core was arranged in a low leakage pattern. The mechanical design of the Region U fuel is essentially the same as that of the Region T fuel, and consists of "value-added" fuel pellets and the "guardian grid" design, first introduced in Cycle 11. The only significant difference is that Region U incorporates an Inconel top grid to mitigate grid-to-rod fretting failures observed at this unit in recent cycles.The implementation instructions provided in this modification support a full core off-load. The safety analysis of this design was performed by W-CE and by FPL using NRC approved methodologies.
The Cycle 16 reload analysis supports a maximum steam generator tube plugging level of 2520 tubes per steam generator (30% average) with a maximum asymmetry of 600 tubes between the two steam generators, and a minimum reactor coolant system (RCS)flow of 335,000 gpm. Additionally, the Cycle 16 reload analysis supports the replacement of the circuit cards for the RCS Low Flow Trip transmitters to add a variable dampening feature, which will increase the total response time from 0.65 second up to 0.90 second.11