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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 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-2024-007, 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 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 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-2023-086, 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
JAN 2 8 2013 FPL. L-2013-034 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 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 4. The COLR is applicable for Unit 4 Cycle 27.
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 344 St Homestead, FL 33035
Attachment to L-2013-034 Page 1 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR Turkey Point Unit 4 Cycle 27 Core Operating Limits Report (COLR) 14B-A1
Attachment to L-2013-034 Page 2 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR
1.0 INTRODUCTION
This Core Operating Limits Report for Turkey Point Unit 4 Cycle 27 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-A5 2.6 4.1.1.3 MTC Surveillance at 300 ppm 14B-A5 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-A6 2.12 3.2.5 DNB Parameters 14B-A6 Figure Description Al Reactor Core Safety Limit - Three Loops in Operation 14B-A7 A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A8 A3 Turkey Point Unit 4 Cycle 27 Rod Insertion Limits vs Thermal Power 14B-A9 A4 Axial Flux Difference as a Function of Rated Thermal Power 14B-A10 14B-A2
Attachment to L-2013-034 Page 3 of 10 TURKEY POINT UNIT 4 CYCLE 27 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-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
- =-- OS, T 2 = OS Lead/Lag compensator on measured AT
-T3 = 2s Lag compensator on measured AT
-K = 1.31
- K2 = 0.023/°F
-T4 = 25s, T5 = 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' > 2235 psig Nominal RCS operating pressure
- fl(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.
14B-A3
Attachment to L-2013-034 Page 4 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR NOTE 2 on TS Table 2.2-1 Overtemperature AT The Overtemperature AT function Allowable Value 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% AT span 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 0.0/ 0 F For increasing average temperature
- K(5=0.0 For decreasing average temperature
- -17 0S Time constants utilized in the lead-lag compensator for Tavg
- K6 =0.001 6/1F For T > T"
- K6 O00 For T < T"
- T" <583.O0 F Indicated Loop Tavg at RATED THERMAL POWER
- f2 (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 14B-A8) 2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)
- > 1.77% Ak/k 14B-A4
Attachment to L-2013-034 Page 5 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR 2.5 Moderator Temperature Coefficient (MTC) (TS 3.1.1.3)
- < +5.0 xl1O5 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 - 41.0 x 10-5 Ak/k/°F EOL, RTP, ARO 2.6 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 14B-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 14B-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 14B-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 14B-A5
Attachment to L-2013-034 Page 6 of 10 TURKEY POINT UNIT 4 CYCLE 27 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 14B-A6
Attachment to L-2013-034 Page 7 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR FIGURE Al Reactor Core Safety Limit - Three Loops in Operation 2455 p*ia 6 6 0 ........ ........ . . .. .........................................-
. ... .. ................................
.... .........................
..... ............
. . . . . .. . .. . . .
226 0 pski UnacceptabeO oaif gNO 2000 ;*sia . ..........
1805 p.sia 620.
0 o 60 0 .... . .. . ... . . ... .. .. . ... . .. ..... .... ...... .. .. ..... ............................. ..... ....
=* ~~Acceptable Operin 5 0... .. .......
.... .....
. .... ......... ... .................
. ... ..........................
............
........................... ......... ...............
..................
.......................................
.................... ...... ...................
.........
- ..................................... mk.................. .
S 40 .........
................. .......
. ....................
.... ...... .. .. . ... .... . . . .....
.....
... .......... . .. .. .........
......... ....
. ... . . ....... . ,
o0 [4
'.2 il; 08 1.0 1.ý 1.4 Core Power (fraction of 2644 MWt) 14B-A7
Attachment to L-2013-034 Page 8 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 2
-W" MODE 4 with no RCP in operatio,,
(0.0, 1.7
- 7) 1
, , .
,- ,- - -.- *- --. --
I L.5 - - - - - - - - - - - - - -
' ~j ; = I . " I i :
z I MODES 1.2, Aand 4with atleast -
- ----LoneRCP in operation --
2 . 1 I75--
1--
.' : , : : , (750,1.0) Th*: ! ,' ' '
0 a
=
w 0.5 ....
...
-- - - - - - - - -
I~I ~
0 .4t" " t"*
a 500 1000 1500 2000 RCS BORON CONCENTRATION (PPM) 14B-A8
Attachment to L-2013-034 Page 9 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR FIGURE A3 Turkey Point Unit 4 Cycle 27 Rod Insertion Limits vs Thermal Power ARO = 229 Steps Withdrawn, Overlap = 101 Steps 230 220 210 200 190 180 170 160 150 CL 140 130 0, 120 C 110 0
100 0 90 80 U 70 M.
60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A9
Attachment to L-2013-034 Page 10 of 10 TURKEY POINT UNIT 4 CYCLE 27 COLR FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 27 120 100 w
Lu 0 80
..
-J
=
60 I--
06 40 a.
20 0 4-40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (%)
14B-A10