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Category:Fuel Cycle Reload Report
MONTHYEARL-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-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 2024-08-12
[Table view] Category:Letter type:L
MONTHYEARL-2024-187, Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-11-12012 November 2024 Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-11-12012 November 2024 Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis L-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-014, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to 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 Cycles2024-02-0909 February 2024 Supplement to 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-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-2024-007, Inservice Inspection Program Owners Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owners 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-2023-172, 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 Owners Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owners 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 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) 2024-09-25
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JUN 2 2 2012 L-2012-258 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 3 Docket No. 50-250 Core Operating Limits Report In accordance with Technical Specification 6.9.1.7, the attached Core Operating Limits Report (COLR) is provided for Turkey Point Unit 3. These curves are applicable for Unit 3 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 Florida Power & Light Company 9760 SW 3 4 4th St., Homestead, FL 33035
TURKEY POINT UNIT 3. CYCLE 26 COLR Appendix A Turkey Point Unit 3 Cycle 26 Core Operating Limits Report (COLR) 14A-A1
TURKEY POINT UNIT 3 CYCLE 26 COLR
1.0 INTRODUCTION
This Core Operating Limits Report for Turkey Point Unit 3 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 14A-A3 2.2 2.2.1 Reactor Trip System Instrumentation Setpoints 14A-A3-14A-A4 2.3 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4 14A-A4 2.4 3.1.1.2 Shutdown Margin Limit for MODE 5 14A-A4 2.5 3.1.1.3 Moderator Temperature Coefficient 14A-A5 2.6 4.1.1.3 MTC Surveillance at 300 ppm 14A-A5 2.7 3.1.3.2 Analog Rod Position Indication System 14A-A5 2.8 3.1.3.6 Control Rod Insertion Limits 14A-A5 2.9 3.2.1 Axial Flux Difference 14A-A5 2.10 3.2.2 Heat Flux Hot Channel Factor Fa(Z) 14A-A5 2.11 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 14A-A6 2.12 3.2.5 DNB Parameters 14A-A6 Figure Description Al Reactor Core Safety Limit - Three Loops in Operation 14A-A7 A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14A-A8 A3 Turkey Point Unit 3 Cycle 26 Rod Insertion Limits vs Thermal Power 14A-A9 A4 Axial Flux Difference as a Function of Rated Thermal Power 14A-A10 14A-A2
TURKEY POINT UNIT 3 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 14A-A7) 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
- T1 = OS, T2 = OS Lead/Lag compensator on measured AT
- T3 = 2s Lag compensator on measured AT
- K, =1.31
- K2 = 0.023/°F
- "4 = 25s, Ts = 3s Time constants utilized in the lead-lag compensator for Tavg
- T6 = 2s Lag compensator on measured Tavg
- T' < 583.0 OF Indicated Loop Tavg at RATED THERMAL POWER
- K3 = 0.00116/psi
- P'Ž 2235 psig Nominal RCS operating pressure
- fd(AI) = 0 for qt - qb between - 18% and + 7%.
For each percent that the magnitude of qt - qb exceeds - 18%,
the AT Trip Setpoint shall be automatically reduced by 3.51%
of its value at RATED THERMAL POWER; and For each percent that the magnitude of qt - qb exceeds +7%,
the AT Trip Setpoint shall be automatically reduced by 2.37%
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.
14A-A3
TURKEY POINT UNIT 3 CYCLE 26 COLR NOTE 2 on TS Table 2.2-1 Overtemperature AT The Overtemperature AT function AllowableValue shall not exceed the nominal trip setpoint by more than 0.5% AT span for the AT channel, 0.2% AT span for the Pressurizer Pressure channel, and 0.4% ATspan for the f(AI) channel. No separate Allowable Value is provided for Tavg because this function is part of the AT value.
NOTE 3 on TS Table 2.2-1 Overpower AT
- K4 = 1.10
- K5 > 0.010 F For increasing average temperature
- Ks = 0.010 F For decreasing average temperature
- T7 2- 0 S Time constants utilized in the lead-lag compensator for Tavg
- K6 = 0.001 6/°F For T > T"
- K 6 = 0.0 ForT <T"
- T" _<583.0°F Indicated Loop Tavg at RATED THERMAL POWER
- f 2 (AI) = 0 For all Al NOTE 4 on TS Table 2.2-1 Overpower AT The Overpower AT function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% AT span for the AT channel. No separate Allowable Value is provided for Tavg because this function is part of the AT value.
2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1.1)
Figure A2 (page 14A-A8) 2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)
- >1.77%Ak/k 14A-A4
TURKEY POINT UNIT 3 CYCLE 26 COLR 2.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)
- < + 5.0 x 105 Ak/k/°F 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/OF
- Less negative than -41.0 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 - 35.0 x 10-5 Ak/k/°F Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.
2.7 Analog Rod Position Indication System (TS 3.1.3.2)
Figure A3 (page 14A-A9) The All Rods Out (ARO) position for all shutdown Banks and Control Banks is defined to be 229 steps withdrawn.
2.8 Control Rod Insertion Limits (TS 3.1.3.6)
Figure A3 (page 14A-A9) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =229 steps withdrawn.
2.9 Axial Flux Difference (TS 3.2.1)
- Figure A4 (page 14A-A10) 2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)
- [FQ]L = 2.30
- K(z) =1.0 For 0' < z < 12' where z is core height in ft 14A-A5
TURKEY POINT UNIT 3 CYCLE 26 COLR 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)
- FAHRTP = 1.248 PFAH = 0.3 DRFA Fuel
- FAHRTP = 1.600 PFAH = 0.3 Upgrade Fuel 2.12 DNB Parameters (TS 3.2.5)
- RCS Tavg < 585.0 OF
- Pressurizer Pressure > 2204 psig 14A-A6
TURKEY POINT UNIT 3 CYCLE 26 COLR Figure Al Reactor Core Safety Limit - Three Loops in Operation C-03
- 0. r.l 3
U) 0 IM 0
540 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 Core Power (fraction of 2644 MWt) 14A-A7
TURKEY POINT UNIT 3 CYCLE 26 COLR Figure A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration
~L.m ILUT7fl I uwrrrFoF _ I I I MODE 4 with no RCP in operation I (0.0, 1.77) 1.5 -1 MODE 1,, 2,i,_
3_and 4witha es
_ LLI I H II IIWJ I II I I III I llrii I z 1111 i L..L lili z 1 0 L *_.
75T0,1.0) _LUJ-----
I-0 CTJT-TLCJJW Inl IILI l l llll tl l l ll ll 1 171- l w
_=
0.5 I I JJJ~ I HI~I HHIIflTHL~*+/-I 111111 II [11 0
0 500 l000 2500 2000 RCS BORON CONCENTRATION (PPM) 14A-A8
TURKEY POINT UNIT 3 CYCLE 26 COLR FIGURE A3 Turkey Point Unit 3 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 229 Steps Withdrawn, Overlap = 101 Steps 230 64.0, 29) 210 .21 2A; 200 ___
190 180 170 __ __ __ __(100.171)
~160 _
S150 __ __ fBank C /
140__Bn U) 130__
2 120__ __ __
110__,*(0, 105) __ __
o B; nk D 30 ____
40/
20 30f P R r 20/
60 10 1412e 0 3 0 5 0 7 0 90 0/
0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14A-A9
TURKEY POINT UNIT 3 CYCLE 26 COLR FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 3 Cycle 26 120
(-9,{00) (+5,10C) 100 0 80
-J UNACCEPTABLE U ACCEPTA LE OPE RATION PERATIOI wu 60
(-30,50) ACCEPTA OPERATION LE 4- (+2N1,50) 2 40 a.
20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (%)
14A-A10