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Category:Fuel Cycle Reload Report
MONTHYEARL-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2022-125, Cycle 31 Core Operating Limits Report2022-09-0606 September 2022 Cycle 31 Core Operating Limits Report L-2021-187, Cycle 26 Core Operating Limits Report2021-09-10010 September 2021 Cycle 26 Core Operating Limits Report L-2021-077, Cycle 30 Core Operating Limits Report2021-04-26026 April 2021 Cycle 30 Core Operating Limits Report L-2020-034, Cycle 25 Core Operating Limits Report2020-02-28028 February 2020 Cycle 25 Core Operating Limits Report L-2019-196, Cycle 29 Core Operating Limits Report2019-10-30030 October 2019 Cycle 29 Core Operating Limits Report L-2018-167, Cycle 24 Core Operating Limits Report2018-09-12012 September 2018 Cycle 24 Core Operating Limits Report L-2018-083, Cycle 28 Core Operating Limits Report2018-04-0202 April 2018 Cycle 28 Core Operating Limits Report L-2017-072, Submittal of Cycle 23 Startup Report2017-04-27027 April 2017 Submittal of Cycle 23 Startup Report L-2016-190, Submittal of Core Operating Limits Report for Cycle 272016-10-14014 October 2016 Submittal of Core Operating Limits Report for Cycle 27 L-2016-048, Submittal of Cycle 22 Core Operating Limits Report2016-02-29029 February 2016 Submittal of Cycle 22 Core Operating Limits Report L-2015-265, Cycle 22 Core Operating Limits Report2015-10-0808 October 2015 Cycle 22 Core Operating Limits Report L-2015-114, Cycle 26 Core Operating Limits Report2015-04-14014 April 2015 Cycle 26 Core Operating Limits Report L-2014-091, Cycle 21 Core Operating Limits Report2014-03-28028 March 2014 Cycle 21 Core Operating Limits Report L-2013-307, Cycle 25 Core Operating Limits Report2013-10-17017 October 2013 Cycle 25 Core Operating Limits Report L-2012-382, Extended Power Uprate Cycle 24 Startup Report2012-10-19019 October 2012 Extended Power Uprate Cycle 24 Startup Report L-2012-298, Cycle 24 Core Operating Limits Report2012-07-25025 July 2012 Cycle 24 Core Operating Limits Report L-2012-083, Cycle 24 Core Operating Limits Report2012-02-27027 February 2012 Cycle 24 Core Operating Limits Report L-2011-066, Cycle 19 Core Operating Limits Report2011-03-0303 March 2011 Cycle 19 Core Operating Limits Report L-2011-021, License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups2011-02-25025 February 2011 License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups L-2010-095, Cycle 23 Core Operating Limits Report2010-05-0505 May 2010 Cycle 23 Core Operating Limits Report L-2009-116, Cycle 18 Core Operating Limits Report2009-05-11011 May 2009 Cycle 18 Core Operating Limits Report 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-2008-254, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 CFR 50.46 Change Report2008-12-0404 December 2008 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 CFR 50.46 Change Report L-2008-244, Cycle 22 Core Operating Limits Report2008-11-0505 November 2008 Cycle 22 Core Operating Limits Report L-2008-052, Cycle 17 Reactor Startup Physics Testing Report2008-03-26026 March 2008 Cycle 17 Reactor Startup Physics Testing Report L-2007-183, Cycle 17 Core Operating Limits Report, Rev. 02007-11-19019 November 2007 Cycle 17 Core Operating Limits Report, Rev. 0 L-2007-121, Cycle 21 Startup Physics Testing Report2007-08-0909 August 2007 Cycle 21 Startup Physics Testing Report L-2007-066, Transmittal of Cycle 21 Core Operating Limits Report2007-04-27027 April 2007 Transmittal of Cycle 21 Core Operating Limits Report L-2006-128, Cycle 16 Core Operating Limits Report2006-05-25025 May 2006 Cycle 16 Core Operating Limits Report L-2005-232, Cycle 20 Core Operating Limits Report2005-11-0909 November 2005 Cycle 20 Core Operating Limits Report L-2004-138, Cycle 19 Core Operating Limits Report - Revision 12004-06-29029 June 2004 Cycle 19 Core Operating Limits Report - Revision 1 L-2004-076, Cycle 19 Core Operating Limits Report, Revision 02004-03-29029 March 2004 Cycle 19 Core Operating Limits Report, Revision 0 L-2003-110, Cycle 14 Core Operating Limits Report2003-05-0101 May 2003 Cycle 14 Core Operating Limits Report L-2002-209, Cycle 18 Core Operating Limits Report - Revision 02002-10-18018 October 2002 Cycle 18 Core Operating Limits Report - Revision 0 2023-03-07
[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
[Table view] |
Text
0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 April 27, 2007 FIPL L-2007-066 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Cycle 21 Core Operating Limits Report Pursuant to St. Lucie Unit 1 Technical Specification (TS) 6.9.1.11.d, Florida Power& Light Company (FPL) is submitting the Core Operating Limits Report (COLR) for operating cycle 21.
Technical Specification 6.9.1.11.d requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance for each reload cycle.
Accordingly, enclosed is a copy of the St. Lucie Unit 1, Cycle 21 Core Operating Limits Report, Revision 0.
Please contact us if there are any questions regarding this submittal.
Very truly yours, GLJ/KWF Attachment A00 an FPL Group company
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment ST. LUCIE UNIT 1, CYCLE 21 CORE OPERATING LIMITS REPORT Revision 0 Prepared By: -
Verified By: &"" - i Approved By:
<2Qj~)06
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment Table of Contents Description Paue 1.0 Introduction 3 2.0 Core Operating Limits 2.1 Moderator Temperature Coefficient 4 2.2 Full Length CEA Position - Misalignment > 15 inches 4 2.3 Regulating CEA Insertion Limits 4 2.4 Linear Heat Rate 4 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 5 2.6 DNB Parameters - AXIAL SHAPE INDEX 5 2.7 Refueling Operations - Boron Concentration 5 2.8 SHUTDOWN MARGIN - Tavg Greater Than 200 OF 5 2.9 SHUTDOWN MARGIN - Tavg Less Than or Equal To 200 OF 5 3.0 List of Approved Methods 12 List of Figures Figure Title Paae 3.1-1a Allowable Time To Realign CEA vs. Initial Fm 6 3.1-2 CEA Insertion Limits vs. THERMAL POWER 7 3.2-1 Allowable Peak Linear Heat Rate vs. Bumup 8 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 9 3.2-3 Allowable Combinations of THERMAL POWER and FrT 10 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 11 Rev 0 Page2 ofi3 St. Lucie St. Unit 1I Cycle Lucie Unit 21 COLR Cycle 21 COLR Rev 0 Page 2 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameter limits for the operation of St. Lucie Unit 1. It contains the limits for the following as provided in Section 2.
Moderator Temperature Coefficient Full Length CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrT DNB Parameter - AXIAL SHAPE INDEX Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Tav, Greater Than 200 OF SHUTDOWN MARGIN - Targ Less Than or Equal To 200 OF This report also contains the necessary figures which give the limits for the above listed parameters.
Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications.
This report is prepared in accordance with the requirements of Technical Specification 6.9.1.11.
C- Rev-- o-----
-t Lu-- Uni C-l ---- 21----
St. Lucie Unit I Cycle 21 COLR Rev 0 Page 3 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 2.0 CORE OPERATING LIMITS 2.1 Moderator Temperature Coefficient (TS 3.1.1.4)
The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/°F at RATED THERMAL POWER.
2.2 Full Length CEA Position - Misalignment > 15 Inches (TS 3.1.3.1)
The time constraints for full power operation with the misalignment of one full length CEA by 15 or more inches from any other CEA in its group are shown in Figure 3.1-la.
2.3 Regulating CEA Insertion Limits (TS 3.1.3.6)
The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1-2, with CEA insertion between the Long Term Steady State Insertion Limits and the Power Dependent Insertion Limits restricted to:
- a. < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval,
- b. < 5 Effective Full Power Days per 30 Effective Full Power Day interval, and
- c. < 14 Effective Full Power Days per calendar year.
2.4 Linear Heat Rate (TS 3.2.1)
The linear heat rate shall not exceed the limits shown on Figure 3.2-1.
The AXIAL SHAPE INDEX power dependent control limits are shown on Figure 3.2-2.
During operation, with the linear heat rate being monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall be maintained within the limits of Figure 3.2-2.
During operation, with the linear heat rate being monitored by the Incore Detector Monitoring System, the Local Power Density alarm setpoints shall be adjusted to less than or equal to the limits shown on Figure 3.2-1.
OR Lui-ntICce2 Rv0Pg f1 St.~~~~~~~-----
St. Lucie Unit 1 Cycle 21 COLR Rev 0 Page 4 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FT (TS 3.2.3)
The calculated value of FrT shall be limited to < 1.70.
The power dependent Frr limits are shown on Figure 3.2-3.
2.6 DNB Parameters - AXIAL SHAPE INDEX (TS 3.2.5)
The AXIAL SHAPE INDEX shall be maintained within the limits specified in Figure 3.2-4.
2.7 Refuelinq Operations - Boron Concentration (TS 3.9.1)
With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:
- a. Either a Kff of 0.95 or less, which includes a 1000 pcm conservative allowance for uncertainties, or
- b. A boron concentration of > 1720 ppm, which includes a 50 ppm conservative allowance for uncertainties.
2.8 SHUTDOWN MARGIN - Tav.- Greater Than 200 OF (TS 3.1.1.1)
The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.
2.9 SHUTDOWN MARGIN - Ta". Less Than or Equal To 200 OF (TS 3.1.1.2)
The SHUTDOWN MARGIN shall be greater than or equal to 2000 pcm.
e e- f StLucie Uni - cyl - -OL St. Lucie Unit I Cycle 21 COLR Rey 0 Page 5 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 1.72
4 4 * .. ..- ........ 4T" .. ... ..
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1.62 1.60 0 10 20 30 40 50 60 70 Time at Full Power to Realign CEA, Minutes FIGURE 3.1-1a Allowable Time to Realign CEA vs. Initial Fr St. Lucie Unit I Cycle 21 COLR Rev 0 Page 6 of 13
) 0 r-dzCD0J.
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$ 4 0 27 55 82 109 137 0 27 55 82 109 137 CEA INSERTION (INCHES)
FIGURE 3.1-2 CEA Insertion Limits vs. THERMAL POWER (4 Reactor Coolant Pumps Operating)
St. Lucie Unit I Cycle 21 COLR Rev 0 Page 7 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 17.0 UNACCEPTABLE OPERATION 16.0 I
15.0 (D
CL ACCEPTABLE OPERATION
'3) 0~ 14.0 13.0 BOL Cycle Life EOL (Fuel + Clad + Moderator)
FIGURE 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup St Lucie Unit I Cycle 21 COLR Rev 0 Page 8 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 1.10 I I I I I I I I I I 1.00 ....................... - ---------- - -----------
Region of II Region of Unacceptable Operation I I I...... I --- Unacceptable Operation Opertio
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-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 Peripheral AXIAL SHAPE INDEX (Not Applicable Below 40% Power)
Note: AXIAL SHAPE INDEX limits for Linear Heat Rate when using Excore Detector Monitoring System)
FIGURE 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level St. Lucie Unit I Cycle 21 COLR Rev 0 Page 9 of 13
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0.6 1.7 1.71 1.72 1.73 1,74 1.75 1.76 1.77 1,78 1.79 Measured FrT FIGURE 3.2-3 Allowable Combinations of THERMAL POWER and FrT S -Uni-uiCycle-
- 21--- Rev--- 0---L Pag 10-St. Lucie Unit I Cycle 21 COLR Rev 0 Pagel10 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 1.10 I . :I I I : I F... .. . [.... L... ........... ..
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0.80 a.t- :.....I . .R egion of I...... I I 0 0.70 O I/I Acceptable: -`---
w
..... (0-----..)- O peration t----------. (0.5,0.65).
I-.
0 ..SI
- i. ... .A.
. . . . . . . ....... .I-----. -..._-.._.-.... I..... ..... ..... ...... .II..... ..... ..... . . ..I.. . . . . .. . .
0.60 S: I 1 I I I I u- t. . . . . ....... . . ........... . .. . ...
.. . : . . r. : ... ...:......
[I ....................... r....................... r. .....
,I: I I t i 0.50 ...-*-
!-- l ---I.. ... ...* ... .. ...*. -------------'------------.-. ---.-
I I I I 0.40
-0 ,6 -0.4 -0.2 0.0 0.2 0..4 0.6 Peripheral AXIAL SHAPE INDEX (Y1)
(Not Applicable Below 40% Power)
(AXIAL SHAPE INDEX limits for DNB)
FIGURE 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER (Four Reactor Coolant Pumps Operating)
St Lucie Unit I Cycle 21 COLR Rev 0 Page 11 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment 3.0 LIST OF APPROVED METHODS The analytical methods used to determine the core operating limits are those previously approved by the NRC, and are listed below.
- 1. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary)
- 2. NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point &
St. Lucie Nuclear Plants," Florida Power & Light Company, January 1995
- 3. XN-75-27(A) and Supplements 1 through 5, [also issued as XN-NF-75-27(A)],
"Exxon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors,"
Exxon Nuclear Company, Inc. /Advanced Nuclear Fuels Corporation, Report and Supplement.1 dated April .977, Supplement.2 dated December*1.980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987 (P)
- 4. ANF-84-73(P)(A) Revision 5, Appendix B, & Supplements 1 and 2, "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, October 1990
- 5. XN-NF-82-21(P)(A) Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, Inc., September 1983
- 6. EMF-84-093(P)(A) Revision 1, "Steam Line Break Methodology for PWRs," Siemens Power Corporation, February 1999 (This document is a Revision to ANF-84-93)
- 7. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, Inc., October 1983
- 8. XN-NF-82-49(P)(A) Revision 1 Supplement 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power Corporation, December 1994
- 9. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transientfor Pressurized Water Reactors," Exxon Nuclear Company, Inc., October 1983
- 10. XN-NF-621(P)(A) Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, Inc., September 1983
- 11. EMF-2087(P)(A) Revision 0, "SEMIPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999 St. Lucie Unit I Cycle 21 COLR Rev 0 Page 12 of 13
St. Lucie Unit 1 Docket No. 50-335 L-2007-066 Attachment
- 12. XN-NF-82-06(P)(A) Revision 1, and Supplements 2,4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, Inc., October 1986
- 13. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991
- 14. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, Inc.,
November 1986
- 15. ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992
- 16. Deleted
- 17. EMF-92-116(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Design," Siemens Power Corporation, February 1999
- 18. EMF-92-153(P)(A) Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005
- 19. EMF-96-029(P)(A) Volumes 1 and 2. "Reactor Analysis System for PWRsVolume 1
- Methodology Description, Volume 2 - Benchmarking Results," Siemens Power Corporation, January 1997
- 20. EMF-1961(P)(A), Revision 0, "Statistical SetpointlTransient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000
- 21. EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," May 2004
- 22. EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," March 2001 St. Lucie Unit I Cycle 21 COLR Rev 0 Page 13 of 13