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| {{#Wiki_filter:0 FPL.POWERING TODAY.EMPOWERING TOMORROW.0 Florida Power & Light Company, 9760 S.W. 344 Street, Florida City, FL 33035 OCT 0 3 2012 L-2012-356 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 | | {{#Wiki_filter:0 Florida Power & Light Company, 9760 S.W. 344 Street, Florida City, FL 33035 OCT 0 3 2012 FPL. L-2012-356 POWERING TODAY. |
| | EMPOWERING TOMORROW. |
| | 0 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 |
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| ==References:== | | ==References:== |
| : 1. Letter from M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-180),"Turkey Point Unit 4 Revised Core Operating Limits Report," April 21, 2012.2. Letter from M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-355),"Turkey Point Unit 4, Nuclear Fuel Pellet Thermal Conductivity Degradation Impact on Current Turkey Point Unit 4 Cycle 26 BE LOCA Analysis Using the 1996 CQD Methodology | | : 1. Letter from M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-180), |
| -10 CFR 50.46 30-Day Special Report," October 3, 2012.Florida Power & Light (FPL) letter L-2012-180 (Reference 1), submitted a revision to the Unit 4 Cycle 26 Core Operating Limits Report (COLR) due to implementation of Amendment 243.In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4 Cycle 26, superseding the COLR transmitted by Reference | | "Turkey Point Unit 4 Revised Core Operating Limits Report," April 21, 2012. |
| : 1. The revision to the Turkey Point Unit 4 Cycle 26 COLR includes changes to accommodate the impact of the fuel pellet thermal conductivity degradation (TCD)as described in Reference 2.Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.
| | : 2. Letter from M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-355), |
| 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 A AU01 1\3 X-, an FPL Group company Attachment to L-2012-356 Page 1 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR Appendix A Revised Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR)14B-A1 Attachment to L-2012-356 Page 2 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR | | "Turkey Point Unit 4, Nuclear Fuel Pellet Thermal Conductivity Degradation Impact on Current Turkey Point Unit 4 Cycle 26 BE LOCA Analysis Using the 1996 CQD Methodology - 10 CFR 50.46 30-Day Special Report," October 3, 2012. |
| | Florida Power & Light (FPL) letter L-2012-180 (Reference 1), submitted a revision to the Unit 4 Cycle 26 Core Operating Limits Report (COLR) due to implementation of Amendment 243. |
| | In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4 Cycle 26, superseding the COLR transmitted by Reference 1. The revision to the Turkey Point Unit 4 Cycle 26 COLR includes changes to accommodate the impact of the fuel pellet thermal conductivity degradation (TCD) as described in Reference 2. |
| | 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 A AU01 1\3 X-, |
| | an FPL Group company |
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| ==1.0 INTRODUCTION==
| | Attachment to L-2012-356 Page 1 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR Appendix A Revised Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR) 14B-A1 |
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| 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 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 Page 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 Attachment to L-2012-356 Page 3 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 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 Overtemperature AT-'13=05OS=O Lead/Lag compensator on measured AT Lag compensator on measured AT-K, =1.24-K 2 =0.017/1F-14 =2 5 s,t5- = 3s-T6 0s-T' < 577.2 OF-K 3= 0.0011psig 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 fd(Al) = 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 Attachment to L-2012-356 Page 4 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR NOTE 3 on TS Table 2.2-1 Overpower AT-K 4 1.10-K 5 -0.02/-F For increasing average temperature | | Attachment to L-2012-356 Page 2 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR |
| -K 5 = 0.0 For decreasing average temperature | | |
| -"7 > 10 S Time constants utilized in the lead-lag compensator for Tavg-K 6 0.00161°F ForT>T"-K 6 0.0 For T < T"-T" _< 577.2 0 F Nominal Tavg at RATED THERMAL POWER-f 2 (AI) = 0 For allAl 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 105 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 10 5 Ak/k/°F to < 0.0 x 10-5 Ak/k/°F-Less negative than -35.0 x 10.5 Ak/k/°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 10-5 Ak/k/OF Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.14B-A4 Attachment to L-2012-356 Page 5 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 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. | | ==1.0 INTRODUCTION== |
| 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]L= 2.47-K(z) = 1.0 (TS 3.2.2)For 0' < z < 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)-FAHRTP = 1.63-PFAH = 0.3 2.12 DNB Parameters (TS 3.2.5)-RCS Tavg < 581.2 OF-Pressurizer Pressure > 2200 psig 14B-A5 Attachment to L-2012-356 Page 6 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 680 670..660 650 640 ,630 620 610 600 590 580 570 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Power (fraction of nominal)1 1.1 1.2 FIGURE Al Reactor Core Safety Limit -Three Loops in Operation 14B-A6 Attachment to L-2012-356 Page 7 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 2.0 (0.0,1.77) 4 z C5 V0 1.5 1.0 HIM [111 1111 IXI I I 1\ I J I IX I I I N I I ACCEPTABLE OPERATION I I I I N 11 1 1 1 1- 1 1 1 1 1 1 1 I I I I N I I I I I I I I I I I I N I I I I I I 1 1 1(750,1.0).
| | 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. |
| 1 1 1 1 1 1 I -.-Lj -F -T-TT--- lill 7 I =T 0.5 0.0 0'500 1000 1500 2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7 Attachment to L-2012-356 Page 8 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 0 U)a-230 220 210 200 190 180 170 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 0 10 20 30 40 50 60 Percent Reactor Power 70 80 90 100 14B-A8
| | 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. |
| * e Attachment to L-2012-356 Page 9 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120 0 80-J 0)20 0o--50-40 20 -10 0 10 20 30 40 50 AMal Rlu Differen (0/4 14B-A9}} | | Section Technical Specification Page 2.1 2.1.1 Reactor Core Safety Limits 14B-A3 2.2 2.2.1 Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 14B-A3-14B-A4 2.3 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4 14B-A4 2.4 3.1.1.2 Shutdown Margin Limit for MODE 5 14B-A4 2.5 3.1.1.3 Moderator Temperature Coefficient 14B-A4 2.6 4.1.1.3 MTC Surveillance at 300 ppm 14B-A4 2.7 3.1.3.2 Analog Rod Position Indication System 14B-A5 2.8 3.1.3.6 Control Rod Insertion Limits 14B-A5 2.9 3.2.1 Axial Flux Difference 14B-A5 2.10 3.2.2 Heat Flux Hot Channel Factor FQ(Z) 14B-A5 2.11 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 14B-A5 2.12 3.2.5 DNB Parameters 14B-A5 Figure Description Al Reactor Core Safety Limit - Three Loops in Operation 14B-A6 A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7 A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power 14B-A8 A4 Axial Flux Difference as a Function of Rated Thermal Power 14B-A9 14B-A2 |
| | |
| | Attachment to L-2012-356 Page 3 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 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 Overtemperature AT Lead/Lag compensator on measured AT |
| | - '13=05OS=O Lag compensator on measured AT |
| | - K, =1.24 |
| | - K2 =0.017/1F |
| | -14 = 2 5 s,t5-= 3s Time constants utilized in the lead-lag compensator for Tavg |
| | - T6 0s Lag compensator on measured Tavg |
| | - T' < 577.2 OF Nominal Tavg at RATED THERMAL POWER |
| | - K3 = 0.0011psig P' _ 2235 psig Nominal RCS operating pressure fd(Al) = 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 |
| | |
| | Attachment to L-2012-356 Page 4 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR NOTE 3 on TS Table 2.2-1 Overpower AT |
| | - K4 1.10 |
| | - K5 - 0.02/-F For increasing average temperature |
| | - K5 = 0.0 For decreasing average temperature |
| | - "7 > 10 S Time constants utilized in the lead-lag compensator for Tavg |
| | - K6 0.00161°F ForT>T" |
| | - K6 0.0 For T < T" |
| | - T" _<577.2 0 F Nominal Tavg at RATED THERMAL POWER |
| | - f2 (AI) = 0 For allAl 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 105 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 10 5 Ak/k/°F to < 0.0 x 10-5 Ak/k/°F |
| | - Less negative than - 35.0 x 10.5 Ak/k/°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 10-5 Ak/k/OF Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm. |
| | 14B-A4 |
| | |
| | Attachment to L-2012-356 Page 5 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 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 (TS 3.2.2) |
| | - [FQ]L= 2.47 |
| | - 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 = 1.63 |
| | - PFAH = 0.3 2.12 DNB Parameters (TS 3.2.5) |
| | - RCS Tavg < 581.2 OF |
| | - Pressurizer Pressure > 2200 psig 14B-A5 |
| | |
| | Attachment to L-2012-356 Page 6 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 680 670 |
| | .. 660 650 640 |
| | ,630 620 610 600 590 580 570 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 |
| | |
| | Attachment to L-2012-356 Page 7 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 2.0 HIM [111 1111 (0.0,1.77) |
| | IXI I I 1\ I 1.5 J I IX III N II ACCEPTABLE OPERATION 4z IIII N 11 1 1 1 1- 1 1 1 1 1 11 IIII N I I I II I II II I C5 I N I II III 1.0 1 1 1(750,1.0). 1 1 11 1 1 V0 0.5 7 |
| | I -.-Lj -F -T-TT--- lill I =T 0.0 0 '500 1000 1500 2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7 |
| | |
| | Attachment to L-2012-356 Page 8 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 230 220 210 200 190 180 170 160 150 140 0 130 120 110 100 U) 90 80 a- 70 60 50 40 30 20 10 0 |
| | 0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A8 |
| | * e Attachment to L-2012-356 Page 9 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120 0 80 |
| | -J 0) 20 0o- |
| | -50 -40 -30 -20 -10 0 10 20 30 40 50 AMal Rlu Differen (0/4 14B-A9}} |
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|---|
Category:Fuel Cycle Reload Report
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L-2019-068, Core Operating Limits Report2019-03-29029 March 2019
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L-2018-195, Core Operating Limits Report2018-10-19019 October 2018
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L-2017-036, Core Operating Limits Report, Cycle 292017-04-14014 April 2017
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L-2016-178, Submittal of Cycle 29 Refueling Outage Steam Generator Tube Inspection Report2016-10-18018 October 2016
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L-2016-176, Submittal of Core Operating Limits Report Cycle 28 and Cycle 292016-09-13013 September 2016
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L-2016-081, Core Operating Limits Report2016-04-14014 April 2016
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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
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L-2012-180, Revised Core Operating Limits Report2012-04-21021 April 2012
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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
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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
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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
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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 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
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L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024
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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
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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,
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
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
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
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
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-2023-094, 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
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Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023
Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.
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-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 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
L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023
Preparation and Scheduling of Operator Licensing Examinations
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-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023
2022 Annual Radiological Environmental Operating Report
L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023
Cycle 33 Core Operating Limits Report
L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023
Radiological Emergency Plan, Revision 75
L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023
Submittal of Periodic Reports
L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023
Correction to U4R33 Steam Generator Tube Inspection Report
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-2023-028, 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-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023
Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application
L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023
Annual Radioactive Effluent Release Report
L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023
Radiological Emergency Plan Revision 73 and Revision 7 4
L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023
Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis
L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023
Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results
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-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022
Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5
L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022
Emergency Response Data System (Eros) Changes
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-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022
and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report
L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022
10 CFR 50.59(d)(2) Summary Report
L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022
Submittal of Periodic Reports
L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022
Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement
L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022
U4R33 Steam Generator Tube Inspection Report
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
L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022
Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication
L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022
Evacuation Time Estimate Study
L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022
Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004
L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022
Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report
L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022
Inservice Inspection Program - Owner'S Activity Report (OAR-1)
L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022
Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2
2024-01-25
[Table view] |
Text
0 Florida Power & Light Company, 9760 S.W. 344 Street, Florida City, FL 33035 OCT 0 3 2012 FPL. L-2012-356 POWERING TODAY.
EMPOWERING TOMORROW.
0 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
References:
- 1. Letter from M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-180),
"Turkey Point Unit 4 Revised Core Operating Limits Report," April 21, 2012.
- 2. Letter from M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-355),
"Turkey Point Unit 4, Nuclear Fuel Pellet Thermal Conductivity Degradation Impact on Current Turkey Point Unit 4 Cycle 26 BE LOCA Analysis Using the 1996 CQD Methodology - 10 CFR 50.46 30-Day Special Report," October 3, 2012.
Florida Power & Light (FPL) letter L-2012-180 (Reference 1), submitted a revision to the Unit 4 Cycle 26 Core Operating Limits Report (COLR) due to implementation of Amendment 243.
In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4 Cycle 26, superseding the COLR transmitted by Reference 1. The revision to the Turkey Point Unit 4 Cycle 26 COLR includes changes to accommodate the impact of the fuel pellet thermal conductivity degradation (TCD) as described in Reference 2.
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 A AU01 1\3 X-,
an FPL Group company
Attachment to L-2012-356 Page 1 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR Appendix A Revised Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR) 14B-A1
Attachment to L-2012-356 Page 2 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR
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 2.1.1 Reactor Core Safety Limits 14B-A3 2.2 2.2.1 Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 14B-A3-14B-A4 2.3 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4 14B-A4 2.4 3.1.1.2 Shutdown Margin Limit for MODE 5 14B-A4 2.5 3.1.1.3 Moderator Temperature Coefficient 14B-A4 2.6 4.1.1.3 MTC Surveillance at 300 ppm 14B-A4 2.7 3.1.3.2 Analog Rod Position Indication System 14B-A5 2.8 3.1.3.6 Control Rod Insertion Limits 14B-A5 2.9 3.2.1 Axial Flux Difference 14B-A5 2.10 3.2.2 Heat Flux Hot Channel Factor FQ(Z) 14B-A5 2.11 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 14B-A5 2.12 3.2.5 DNB Parameters 14B-A5 Figure Description Al Reactor Core Safety Limit - Three Loops in Operation 14B-A6 A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7 A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power 14B-A8 A4 Axial Flux Difference as a Function of Rated Thermal Power 14B-A9 14B-A2
Attachment to L-2012-356 Page 3 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 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 Overtemperature AT Lead/Lag compensator on measured AT
- '13=05OS=O Lag compensator on measured AT
- K, =1.24
- K2 =0.017/1F
-14 = 2 5 s,t5-= 3s Time constants utilized in the lead-lag compensator for Tavg
- T6 0s Lag compensator on measured Tavg
- T' < 577.2 OF Nominal Tavg at RATED THERMAL POWER
- K3 = 0.0011psig P' _ 2235 psig Nominal RCS operating pressure fd(Al) = 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
Attachment to L-2012-356 Page 4 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR NOTE 3 on TS Table 2.2-1 Overpower AT
- K4 1.10
- K5 - 0.02/-F For increasing average temperature
- K5 = 0.0 For decreasing average temperature
- "7 > 10 S Time constants utilized in the lead-lag compensator for Tavg
- K6 0.00161°F ForT>T"
- K6 0.0 For T < T"
- T" _<577.2 0 F Nominal Tavg at RATED THERMAL POWER
- f2 (AI) = 0 For allAl 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 105 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 10 5 Ak/k/°F to < 0.0 x 10-5 Ak/k/°F
- Less negative than - 35.0 x 10.5 Ak/k/°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 10-5 Ak/k/OF Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.
14B-A4
Attachment to L-2012-356 Page 5 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 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 (TS 3.2.2)
- [FQ]L= 2.47
- 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 = 1.63
- PFAH = 0.3 2.12 DNB Parameters (TS 3.2.5)
- RCS Tavg < 581.2 OF
- Pressurizer Pressure > 2200 psig 14B-A5
Attachment to L-2012-356 Page 6 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 680 670
.. 660 650 640
,630 620 610 600 590 580 570 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
Attachment to L-2012-356 Page 7 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR 2.0 HIM [111 1111 (0.0,1.77)
IXI I I 1\ I 1.5 J I IX III N II ACCEPTABLE OPERATION 4z IIII N 11 1 1 1 1- 1 1 1 1 1 11 IIII N I I I II I II II I C5 I N I II III 1.0 1 1 1(750,1.0). 1 1 11 1 1 V0 0.5 7
I -.-Lj -F -T-TT--- lill I =T 0.0 0 '500 1000 1500 2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7
Attachment to L-2012-356 Page 8 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 230 220 210 200 190 180 170 160 150 140 0 130 120 110 100 U) 90 80 a- 70 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A8
- e Attachment to L-2012-356 Page 9 of 9 TURKEY POINT UNIT 4 CYCLE 26 COLR FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120 0 80
-J 0) 20 0o-
-50 -40 -30 -20 -10 0 10 20 30 40 50 AMal Rlu Differen (0/4 14B-A9
