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Category:Fuel Cycle Reload Report
MONTHYEARL-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2022-052, Core Operating Limits Report2022-04-0101 April 2022 Core Operating Limits Report L-2021-195, Submittal of Core Operating Limits Report2021-10-22022 October 2021 Submittal of Core Operating Limits Report L-2020-149, Submittal of Core Operating Limits Report2020-10-13013 October 2020 Submittal of Core Operating Limits Report L-2020-052, Core Operating Limits Report2020-04-10010 April 2020 Core Operating Limits Report L-2019-068, Core Operating Limits Report2019-03-29029 March 2019 Core Operating Limits Report L-2018-195, Core Operating Limits Report2018-10-19019 October 2018 Core Operating Limits Report L-2017-036, Core Operating Limits Report, Cycle 292017-04-14014 April 2017 Core Operating Limits Report, Cycle 29 L-2016-178, Submittal of Cycle 29 Refueling Outage Steam Generator Tube Inspection Report2016-10-18018 October 2016 Submittal of Cycle 29 Refueling Outage Steam Generator Tube Inspection Report L-2016-176, Submittal of Core Operating Limits Report Cycle 28 and Cycle 292016-09-13013 September 2016 Submittal of Core Operating Limits Report Cycle 28 and Cycle 29 L-2016-081, Core Operating Limits Report2016-04-14014 April 2016 Core Operating Limits Report L-2015-271, Core Operating Limits Report, Cycle 282015-11-16016 November 2015 Core Operating Limits Report, Cycle 28 L-2014-069, Core Operating Limits Report2014-03-26026 March 2014 Core Operating Limits Report L-2013-034, Core Operating Limits Report for Unit 4 Cycle 272013-01-28028 January 2013 Core Operating Limits Report for Unit 4 Cycle 27 L-2012-356, Revised Core Operating Limits Report2012-10-0303 October 2012 Revised Core Operating Limits Report L-2012-258, Core Operating Limits Report2012-06-22022 June 2012 Core Operating Limits Report L-2012-204, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 2011 Annual Report2012-04-30030 April 2012 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 2011 Annual Report L-2012-180, Revised Core Operating Limits Report2012-04-21021 April 2012 Revised Core Operating Limits Report L-2011-118, Core Operating Limits Report2011-04-11011 April 2011 Core Operating Limits Report L-2011-067, 2010 Annual Fitness for Duty Performance Report2011-02-24024 February 2011 2010 Annual Fitness for Duty Performance Report L-2011-006, License Amendment Request No. 209; Relocation of Cycle Specific Parameters to the Core Operating Limits Report (COLR)2011-02-21021 February 2011 License Amendment Request No. 209; Relocation of Cycle Specific Parameters to the Core Operating Limits Report (COLR) L-2011-019, Cycle 25 Sartup Report2011-02-0404 February 2011 Cycle 25 Sartup Report L-2010-230, Core Operating Limits Report2010-10-11011 October 2010 Core Operating Limits Report L-2009-240, Core Operating Limits Report for Turkey Point Unit 42009-11-13013 November 2009 Core Operating Limits Report for Turkey Point Unit 4 L-2009-076, Submittal of Core Operating Limits Report2009-04-0707 April 2009 Submittal of Core Operating Limits Report L-2008-087, Core Operating Limits Report, Cycle 242008-04-24024 April 2008 Core Operating Limits Report, Cycle 24 L-2007-150, Submittal of Core Operating Limits Report2007-09-27027 September 2007 Submittal of Core Operating Limits Report L-2005-088, Core Operating Limits Report2005-05-20020 May 2005 Core Operating Limits Report L-2004-219, Core Operating Limits Report2004-10-12012 October 2004 Core Operating Limits Report L-2003-254, Core Operating Limits Report for Cycle 212003-10-20020 October 2003 Core Operating Limits Report for Cycle 21 L-2003-040, Core Operating Limits Report2003-03-13013 March 2003 Core Operating Limits Report L-2002-063, Core Operating Limits Report for Turkey Point, Unit 42002-04-0404 April 2002 Core Operating Limits Report for Turkey Point, Unit 4 2023-04-27
[Table view] Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, 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, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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 IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
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0 FPL.POWERING TODAY.EMPOWERING TOMORROWS Florida Power and Light Company, 9760 SW 3 4 4 th St., Homestead, FL 33035 APR 2 1 2012 L-2012-180 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 4 Docket No. 50-251 Revised Core Operating Limits Report
Reference:
Florida Power & Light Letter 2011-118 to USNRC, dated April 11, 2011,"Core Operating Limits Report" In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4, superseding the COLR transmitted by the reference letter. This revised COLR includes additional parameters that have been relocated from the Turkey Point Technical Specifications per Amendment 243 and is applicable during Cycle 26.Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.
Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company Appendix A Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR)14B-A1
1.0 INTRODUCTION
This Core Operating Limits Report for Turkey Point Unit 4 Cycle 26 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7.The Technical Specifications (TS) affected by this report are listed below with the section and page for each one of the TS addressed in this COLR document.Section Technical Specification Page 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 2.1.1 2.2.1 3.1.1.1 3.1.1.2 3.1.1.3 4.1.1.3 3.1.3.2 3.1.3.6 3.2.1 3.2.2 3.2.3 3.2.5 Reactor Core Safety Limits Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 Shutdown Margin Limit for MODES 1, 2, 3, 4 Shutdown Margin Limit for MODE 5 Moderator Temperature Coefficient MTC Surveillance at 300 ppm Analog Rod Position Indication System Control Rod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor FQ(Z)Nuclear Enthalpy Rise Hot Channel Factor DNB Parameters Description Reactor Core Safety Limit -Three Loops in Operation Required Shutdown Margin vs Reactor Coolant Boron Concentration Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power Axial Flux Difference as a Function of Rated Thermal Power 14B-A3 14B-A3-14B-A4 14B-A4 14B-A4 14B-A4 14B-A4 14B-A5 14B-A5 14B-A5 14B-A5 14B-A5 14B-A5 14B-A6 14B-A7 14B-A8 14B-A9 Figure Al A2 A3 A4 14B-A2
2.0 OPERATING
LIMITS The cycle-specific parameter limits for the specifications listed in the Introduction are presented below and listed sequentially by Technical Specification (TS). These limits have been developed using the NRC-approved methodologies specified in TS 6.9.1.7.2.1 Reactor Core Safety Limits -Three Loops in Operation (TS 2.1.1)-Figure Al (page 14B-A6)In Modes 1 and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure Al.2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1)NOTE 1 on TS Table 2.2-1 OvertemDerature AT-T1I=OS, T2 =OS-T3 =Os-K, =1.24-K 2 =0.0171 0 F-T4 =25s,t 5 ,= 3s-T6 =0O-T'!g577.2 OF-K 3= 0.0l/PSig Lead/Lag compensator on measured AT Lag compensator on measured AT Time constants utilized in the lead-lag compensator for Tavg Lag compensator on measured Tavg Nominal Tavg at RATED THERMAL POWER P' >_ 2235 psig Nominal RCS operating pressure-f 1 (AI) = 0 for qt -qb between -50% and + 2%.For each percent that the magnitude of qt -qb exceeds -50%, the AT Trip Setpoint shall be automatically reduced by 0.0%of its value at RATED THERMAL POWER; and For each percent that the magnitude of qt -qb exceeds + 2%, the AT Trip Setpoint shall be automatically reduced by 2.19%of its value at RATED THERMAL POWER.Where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER.14B-A3 NOTE 3 on TS Table 2.2-1 Overpower AT-1(45 1.10-Ks5 -0.021°F For increasing average temperature
-K5 = 0.0 For decreasing average temperature
-T 7 > 10 S Time constants utilized in the lead-lag compensator for Tavg-K 6 = 0.001 61°F For T > T"-K 6 = 0.0 For T < T"-T" _ 577.2 0 F Nominal Tavg at RATED THERMAL POWER-f 2 (Al) = 0 For all Al 2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1.1)-Figure A2 (page 14B-A7)2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)-> 1% Ak/k 2.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)-< + 5.0 x 10- Ak/k/OF BOL, HZP, ARO and from HZP to 70% Rated Thermal Power (RTP)-From 70% RTP to 100% RTP the MTC decreasing linearly from < + 5.0 x 10s Ak/k/°F to < 0.0 x 10 5 Ak/k/°F-Less negative than -35.0 x 10 5 AkIk/0 F EOL, RTP, ARO 2.6 Moderator temperature coefficient (MTC) Surveillance at 300 ppm (TS 4.1.1.3)Less negative than -30.0 x 10s Ak/k/°F Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.14B-A4
2.7 Analog
Rod Position Indication System (TS 3.1.3.2)-Figure A3 (page 14B-A8) The All Rods Out (ARO) position for all shutdown Banks and Control Banks is defined to be 228 steps withdrawn.
2.8 Control
Rod Insertion Limits (TS 3.1.3.6)-Figure A3 (page 14B-A8) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =228 steps withdrawn.
2.9 Axial
Flux Difference (TS 3.2.1)-Figure A4 (page 14B-A9)2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)-[FQ]L = 2.50-K(z) =1.0 For 0' < z < 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)-FAHRTP = 1.70-PFAH = 0.3 2.12 DNB Parameters (TS 3.2.5)-RCS Tavg < 581.2 °F-Pressurizer Pressure > 2200 psig 14B-A5 680 670'660-2455 psia 660 I UNACCEPTABLE 5 0 OPERATION 2250 psia 640%a 630 -t2000 psia 620 I--610 -1805 Psia- 1 600 ACCEPTABLE\
590 OPERATION
-580V 570 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 Power (fraction of nominal)FIGURE Al Reactor Core Safety Limit -Three Loops in Operation 14B-A6 2.0 (0..O1 .77)z 1.5 I A I ACCEPTABLE OPERATION:
I I I I III I If I I I I I I H t -I I I I I I I I I J i- i-I l l I I I 1 1 1 1 1 1 1 1 1 H IM 1 '1111 1 11 i f ; I I I 1 1 1 1 i l l f i l l I I I I I I I I f i l l 1 1 1 i f I 111H HIM. HIM III I f 1 1 1 1 11 1 1 H i l l If 1.0 0.5..~~50 .......0.. ......0. ..0.0 0 500 1000 1500 2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7 FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 230 __ __ __220 _63.52 210_ (5 X.212 ?2U 200 -.190 180 Batk C 170 _ _La 160 ____ _S150o- -140- -_u, 130 /2 120 ___11o _- , o0 100 -90 I80 -/ -.....'nk3 70 __ix 60 -50 40 __30 /20 /10 1 ._0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A8 FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120-(-l1)100)
(+7,10)100 60 80__1-
/ I.IACCEPELE OPERATIN('U 640 J -o ) ACCEPTABLE 00660) OEAON kS))C 20 0--50 30 10 0 10 20 30 40 50 Aial Rx ifference (9/1 14B-A9