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Category:Annual Report
MONTHYEARL-2015-142, 2014 Annual Environmental Operating Report2015-04-28028 April 2015 2014 Annual Environmental Operating Report L-2015-050, Annual Fitness-For-Duty-Program Report for the Period of January 1 Through December 31, 20142015-02-24024 February 2015 Annual Fitness-For-Duty-Program Report for the Period of January 1 Through December 31, 2014 L-2013-092, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2013-03-18018 March 2013 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2012-091, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2012-03-0101 March 2012 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2010-033, Cy 2009 Corrections to Annual Radioactive Effluent Release Report (L-2010-033 Dated February 25, 2010) Section 8. Process Control Program (PCP) Revisions, Page 8 of 59 and AP 0520025 Revision 13C with mark-up2010-02-25025 February 2010 Cy 2009 Corrections to Annual Radioactive Effluent Release Report (L-2010-033 Dated February 25, 2010) Section 8. Process Control Program (PCP) Revisions, Page 8 of 59 and AP 0520025 Revision 13C with mark-up ML0816504352008-07-21021 July 2008 Allegation Program Annual Trends Report Cy 2007 L-2008-029, St. Lucie, Units 1 & 2, 2007 Annual Radioactive Effluent Release Report2008-02-27027 February 2008 St. Lucie, Units 1 & 2, 2007 Annual Radioactive Effluent Release Report ML0806605792008-02-27027 February 2008 St. Lucie, Units 1 & 2, 2007 Annual Radioactive Effluent Release Report L-2007-051, Annual Radiological Environmental Operating Report for Calendar Year 20062007-03-29029 March 2007 Annual Radiological Environmental Operating Report for Calendar Year 2006 L-2007-040, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2007-03-22022 March 2007 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2005-260, Price Anderson Guarantees/Annual Financial Report2005-12-29029 December 2005 Price Anderson Guarantees/Annual Financial Report L-2005-166, Report of 10 CFR 50.59 Plant Changes2005-08-11011 August 2005 Report of 10 CFR 50.59 Plant Changes L-2003-290, Report of 10 CFR 50.59 Plant Changes2003-12-0202 December 2003 Report of 10 CFR 50.59 Plant Changes L-2003-078, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2003-03-26026 March 2003 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report ML18096B5831975-11-19019 November 1975 St. Lucie, Units 1 & 2 - 11/19/1975 Letter Submittal of Annual Financial Report for 1974 ML18227A9921975-11-19019 November 1975 Submit 1974 Annual Report. ML18096B4031970-12-31031 December 1970 Hutchinson Island Units 1 and 2 - Exhibit II Facts & Figures Florida Power & Light Company Supplement to Annual Report for 1970, Exhibit III, and Exhibit IV ML18096B4021970-12-31031 December 1970 1970 Annual Report Florida Power & Light Company 2015-04-28
[Table view] Category:Letter type:L
MONTHYEARL-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-2024-110, 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-2024-114, 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-2024-109, 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-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, 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-2024-010, 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-2023-107, 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-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-114, 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 2024-08-07
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Text
Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 August 11, 2005 FPL L-2005-166 10 CFR 50.59(d)
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 ChanQes 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 June 9, 2003 through February 15, 2005. This submittal correlates with the information included in Amendment 16 of the Updated Final Safety Analysis Report submitted under separate cover.
Please contact us should there by any questions regarding this information.
William J~efs(
Vice President St. Lucie Plant WJ/tit Attachment
"--I (.:::-
- ,I-- - q-an FPL Group company
St. Lucie Plant Docket No. 389 L-2005-166 Attachment ST. LUCIE UNIT 2 DOCKET NUMBER 50-389 CHANGES, TESTS AND EXPERIMENTS MADE AS ALLOWED BY 10 CFR 50.59 FOR THE PERIOD OF JUNE 9, 2003 THROUGH FEBRUARY 15, 2005 I
St. Lucie Plant Docket No. 389 L-2005-166 Attachment 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 June 9, 2003 through February 15, 2005.
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. And 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 prior NRC approval is not required.
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St. Lucie Plant Docket No. 389 L-2005-166 Attachment TABLE OF CONTENTS SECTION 1 PLANT CHANGEIMODIFICATIONS PAGE 02086 Fuel Cask Crane Replacement 5 SECTION 2 50.59 EVALUATIONS PAGE SENS-00-013 Use of PRC-01 Resin in the CVCS Letdown 7 Stream to Remove Co-58 Contaminants SEES-05-008 Installation of M&TE Inside Containment 8 for SL2-15 and SL2-16 SECTION 3 RELOAD EVALUATION PAGE 04078 St Lucie Unit 2 Cycle 15 Reload 10 3
St. Lucie Plant Docket No. 389 L-2005-166 Attachment SECTION 1 PLANT CHANGE/MODIFICATIONS 4
St. Lucie Plant Docket No. 389 L-2005-166 Attachment PLANT CHANGE/MODIFICATION 02086 REVISIONS 0 & I FUEL CASK CRANE REPLACEMENT Summary:
This PC/M provides modifications to the spent fuel pool cask handling crane system.
Specifically, this change package involves the installation of a new safety related 150/25 ton single-failure proof crane that is designed for handling spent fuel dry storage casks. This PC/M is for the installation of the new crane only.
Other activities related to this installation such as removal of the original crane and modification of the crane runway/support structure have been accomplished under other PC/Ms.
This evaluation included analysis of any potential impact of surrounding safety related components for accidental load drop/impact during installation and for underground utilities and plant roads impact from mobile crane and other heavy equipment transport.
Revision 1 provided for the deletion of the cask drop analysis described in UFSAR Sections 9.1.4.3.2 and 15.7.4.1.3. Since the new crane is single-failure proof, a load drop analysis is not required, as was the case with the original, non single-failure proof crane. Acknowledgement/agreement between FPL and the NRC concerning this deletion took place via license amendment 134, which was approved by the NRC in April 2004. Other Revision I changes were administrative in nature.
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St. Lucie Plant Docket No. 389 L-2005-166 Attachment SECTION 2 50.59 EVALUATIONS 6
St. Lucie Plant Docket No. 389 L-2005-166 Attachment EVALUATION SENS-00-013 REVISION 3 USE OF PRC-01 RESIN IN THE CVCS LETDOWN STREAM 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 issued in 2004 and is thus included in this report.
This evaluation was prepared to examine the use of an additional resin material in the chemical and volume control system (CVCS) ion exchangers during the plant cooldown and refueling evolution. The material utilized is an acrylic substrate weak acid resin identified as PRC-01 that will increase the decontamination factor (DF) of the CVCS cleanup system for sub-micron sized particulates of Cobalt 58.
Particulates are not efficiently removed by resins in the current mixed bed ion exchanger and, depending on particle size, may not be removed by installed CVCS purification filters. The PRC-01 resin proposed for use has a demonstrated high affinity for corrosion products in the particulate form. Use of this resin material will assist in reducing the occupational dose incurred during refueling outages.
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 removes 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 provides some minor administrative documentation changes.
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St. Lucie Plant Docket No. 389 L-2005-166 Attachment EVALUATION PSL-ENG-SEES-05-008 REVISION 0 INSTALLATION OF M&TE INSIDE CONTAINMENT FOR SL2-15 AND SL2-16 Summary:
As a result of a Turkey Point plant condition report it was determined that there are two locations inside the Unit 2 containment where conduit is routed very close to RCS piping.
This condition could result in long-term thermal aging concerns for the affected cables.
This evaluation provides for the temporary installation of four battery-powered, self-contained temperature data loggers and associated temperature monitoring equipment (i.e., cable and sensors) inside containment. This equipment will remain inside containment for the SL2-15 and SL2-16 fuel cycles. Data will be downloaded after the SL2-15 fuel cycle and again after the SL2-16 fuel cycle, at which time the equipment will be removed.
The data loggers will:
- 1. provide accurate, location-specific temperature data, and
- 2. provide a basis for determining what corrective actions may be required.
Each of the four data loggers and remote temperature probes have been installed by splicing IEEE 383 qualified cable to the 1-foot of vendor supplied cable.
The evaluation includes an assessment of the following:
- 1. seismic interaction,
- 2. loads to existing structures/components,
- 3. hydrogen generation,
- 4. containment free volume and heat sink analysis,
- 5. combustible material loading,
- 6. interaction with the containment sump and effects on post-accident flow of water,
- 7. containment flood elevation,
- 8. electrical separation/interaction, and
- 9. chemistry/material impacts.
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St. Lucie Plant Docket No. 389 L-2005-166 Attachment SECTION 3 RELOAD EVALUATION 9
St. Lucie Plant Docket No. 389 L-2005-166 Attachment PLANT CHANGEIMODIFICATION 04078 REVISIONS 0,1 & 2 ST. LUCIE UNIT 2 CYCLE 15 RELOAD Summary:
This package provided the reload core design for St. Lucie Unit 2 Cycle 15 developed by Florida Power & Light Company (FPL) and Westinghouse Electric - Combustion Engineering (W-CE). The Cycle 15 core was designed for a nominal cycle length of 10,710 EFPH, based on a Cycle 14 length of 12,543 EFPH.
The primary design change to the core for Cycle 15 was the replacement of 72 irradiated fuel assemblies with 68 fresh Region T assemblies and 4 irradiated Region P fuel assemblies that were residing in the spent fuel pool. The fuel in the Cycle 15 core was arranged in a low leakage pattern. The mechanical design of the Region T fuel is essentially the same as that of the Region S fuel, and consists of "value-added" fuel pellets and the uguardian grid" design, first introduced in Cycle 11.
The implementation instructions provided in this modification required a full core off-load. The safety analysis of this design was performed by W-CE and by FPL using NRC approved methodologies.
The analyses for Cycle 15 support a maximum steam generator tube plugging level of 2,520 tubes per steam generator (30% average) with a maximum asymmetry of 600 tubes, including the corresponding reduction in RCS flow. The reduction in RCS flow was approved by the NRC in January 2005 via Technical Specification Amendment 138.
Revision 1 incorporated a redesigned core loading pattern. The reason for this change was the extended Cycle 14 operating cycle, which resulted in a reduced energy requirement for Cycle 15. The redesigned core was analyzed to meet all applicable design requirements.
Revision 2 addressed changes corresponding to the final 30% steam generator tube plugging analysis approved by the NRC. This revision also addressed unrecovered debris in the lower reactor vessel and its potential impact on fuel.
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