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#REDIRECT [[L-2016-176, Submittal of Core Operating Limits Report Cycle 28 and Cycle 29]]
| number = ML16265A606
| issue date = 09/13/2016
| title = Turkey Point, Units 3 and 4 - Submittal of Core Operating Limits Report Cycle 28 and Cycle 29
| author name = Summers T
| author affiliation = Florida Power & Light Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000250, 05000251
| license number =
| contact person =
| case reference number = L-2016-176
| document type = Fuel Cycle Reload Report, Letter
| page count = 22
}}
 
=Text=
{{#Wiki_filter:.. U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Core Operating Limits Reports
 
==References:==
September 13, 2016 L-2016-176 10 CFR 50.36 1. Florida Power and Light Company (FPL) letter L-2015-271, "Turkey Point Unit 3 Docket No. 50-250, Core Operating Limits Report," dated November 16, 2015. 2. Florida Power and Light Company (FPL) letter L-2016-081, "Turkey Point Unit 4 Docket No. 50-251', Core Operating Limits Report," dated April 14, 2016. 3. USNRC letter, "Turkey Point Nuclear Generating Unit Nos. 3 and 4 -Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements (CAC NOS. MF6783 and MF6784,." Dated June 20, 2016. In accordance with Technical Specification 6.9.1.7, the Core Operating Limits Report (COLR) for Turkey Point Unit 3 Cycle 28 was submitted by Reference 1. The COLR for Turkey Point Unit 4 Cycle 29 was submitted by Reference 2. On June 20, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Amendments 271 and 266 to Renewed Facility Operating Licenses (RFOLs) No. DPR-31 and DPR-41 for Turkey Point Units 3 and 4, respectively (Reference 3). License Amendments 271 and 266 revised Technical Specification (TS) 3/4.1, "Reactivity Control Systems, Moderator Temperature Coefficient," Surveillance Requirement 4.1.1.3.b to allow the near end-of-life Moderator Temperature Coefficient (MTC) measurement requirement to not be performed by placing a set of conditions on reactor core operation. The amendments also revised TS 6.9.1. 7, "Core Operating Limits Report," to include the analytical methods used to support the suspension of the near end-of-life MTC. In addition, the amendments require that the physics codes used to support the suspension of the near end-of-life MTC be specified in the COLR for the current cycle. Florida Power & Light Company 9760 SW 344 St Homestead, FL 33035 
. ' L-2016-176 Page2 Amendments 271 and 266 have been implemented; therefore, in accordance with Technical Specification 6.9. 1. 7, this letter provides the updated COLRs for Turkey Point Units 3 and 4. Attachment 1 provides the revised COLR for Turkey Point Unit 3. The COLR is applicable for Unit 3 Cycle 28. Attachment 2 provides the revised COLR for Turkey Point Unit 4. The COLR is applicable for Unit 4 Cycle 29. The attachments to this letter replace the COLRs submitted by References 1 and 2 in their entirety. Should there be any questions, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698. Sincerely, Ahomas Summers Site Vice President Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant    to L-2016-176 Page 1 of 10 Revised Turkey Point Unit 3 Cycle 28 Core Operating Limits Report (COLR) 14A-A1 
. ' Attachment 1 to L-2016-176 Page 2of10
 
==1.0 INTRODUCTION==
This Core Operating Limits Report for Turkey Point Unit 3 Cycle 28 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 2.1.1 2.2 2.2.1 2.3 3.1.1.1 2.4 3.1.1.2 2.5 3.1.1.3 2.6 4.1.1.3 2.7 3.1.3.2 2.8' 3.1.3.6 2.9 3.2.1 2.10 3.2.2 2.11 3.2.3 2.12 3.2.5 Figure A1 A2 A3 A4 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 F0(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 3 Cycle 28 Rod Insertion Limits vs Thermal Power Axial Flux Difference as a Function of Rated Thermal Power 14A-A2 .Page 14A-A3 14A-A3-14A-A4 14A-A4 14A-A4 14A-A5 14A-A5 14A-A5 14A-A5 14A-A5 14A-A6 14A-A6 14A-A6 14A-A7 14A-A8 14A-A9 14A-A10 2.0 OPERATING LIMITS Attachment 1 to L-2016-176 Page 3of10 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 NRG-approved methodologies specified in TS 6.9.1. 7. 2.1 Reactor Core Safety Limits -Three Loops in Operation (TS 2.1.1) Figure A 1 (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 A 1. 2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1) NOTE 1 on TS Table 2.2-1 Overtemperature L1T *1 = Os, *2 = Os Lead/Lag compensator on measured L1 T 't3 = 2s Lag compensator on measured L1 T K1=1.31 K2 = 0.023/°F 't4 = 25s, *s = 3s Time constants utilized in the lead-lag compensator for T avg *e = 2s Lag compensator on measured Tavg T':::;; 583.0 °F Indicated Loop Tavg at RATED THERMAL POWER K3 = 0.00116/psi P' ;:::: 2235 psig Nominal RCS operating pressure f1(111) = 0 for qt -qb between -18% and + 7% For each percent that the magnitude of qt -qb exceeds -18%, the L1T Trip Setpoint shall be automatically reduced by 3.51% of its value at RA TED THERMAL POWER; and For each percent that the magnitude of qt -qb exceeds + 7%, the L1 T Trip Setpoint shall be automatically reduced by 2.37% of its value at RA TED 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    to L-2016-176 Page 4of10 NOTE 2 on TS Table 2.2-1 Overtemperature LiT (Not affected by COLR. included for completeness) The Overtemperature LiT function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% Li T span for the Li T channel, 0.2% Li T span for the Pressurizer Pressure channel, and 0.4% Li T span for the f(Lil) channel. No separate Allowable Value is provided for T avg because this function is part of the Li T value. NOTE 3 on TS Table 2.2-1 Overpower LiT Ks 0.0/°F For increasing average temperature Ks= 0.0 For decreasing average temperature *7 0 s Time constants utilized in the lead-lag compensator fo_r T avg Ka= 0.0016/°F For T > T" For T:.::; T" T":.::; 583.0 °F Indicated Loop Tavg at RATED THERMAL POWER fz (iii)= 0 For all Lil NOTE 4 on TS Table 2.2-1 Overpower LiT (Not affected by COLR. included for completeness) The Overpower Li T function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% Li T span for the Li T channel. No separate Allowable Value is provided for T avg because this function is part of the Li T 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% Lik/k 14A-A4 2.5 Moderator Temperature Coefficient (MTC) (TS 3.1.1.3) + 5.0 X 10-5 i1k/k/°F From 70% RTP to 100% RTP the MTC decreasing linearly 5.0 X 10-5 i1k/k/°F 0.0 X 10-5 i1k/k/°F Less negative than -41.0 x 1 ff5 i1k/k/°F 2.6 MTC Surveillance at 300 ppm (TS 4.1.1.3) Attachment 1 to L-2016-176 Page 5of10 BOL, HZP, ARO, and from HZP to 70% Rated Thermal Power (RTP) EOL, RTP, ARO Less negative than -35.0 x 10-5 i1k/k/°F(-35 pcm/°F) Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm. The Revised Predicted near -EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP-13749-P-A: Revised Predicted MTC = Predicted MTC + AFD Correction -3 pcm/°F If the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limit and all the benchmark criteria contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 4.1.1.3.b is not required to be performed. The neutronics methods used with WCAP-13749-P-A are those described in WCAP-11596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988. 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 228 steps withdrawn. 2.8 Control Rod Insertion Limits (TS 3.1.3.6) Figure A3 (page 14A-A9) 2.9 Axial Flux Difference (TS 3.2.1) Figure A4 (page 14A-A 10) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =228 steps withdrawn. 14A-A5 2.10 Heat Flux Hot Channel Factor Fa(Z} (TS 3.2.2) [Fa]L = 2.30 Attachment 1 to L-2016-176 Page 6of10 K(z) = 1.0 For O' .:::_ z .:::_ 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3) Ft.HRTP = 1.600 PFt.H = 0.3 2.12 DNB Parameters (TS 3.2.5) RCS Tavg .:::_ 585.0 °F Pressurizer Pressure 2204 psig 14A-A6 2455 psia Acceptable Operation 0.0 0.2 0.4 Attachment 1 to L-2016-176 Page 7 of 10 Unacceptable Operation 0.6 0.6 1.0 1.2 1.4 Core Power (fraction of 2644 MWt) FIGURE A1 Reactor Core Safety Limit-Three Loops in Operation 14A-A7 2 (0.0, 1.77) 1.5 --z ::; z 1 0 Q ..... => :c: V) 0 l.U 0: -s 0.5 a: 0 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration Attachment 1 to L-2016-176 Page 8 of 10 -i-l----I , . ,.J_l __ !--' -MODE 4 with no RCP.in operation ri -------. ---i-------r--1----1-1-r------1----1-----1 ,-,----.-. 1-.---:-.----,---r--n---.-n---r--1-----__ J =-' I I i ' l I I =t=c= =iF-1
* 1 ----------,---i----r.-,--,--i---r--,---l--1---r----R--i-w_ _ __ i ; ' -*----:-. MODES 1. 2. 3. and 4 with at least -1 , , l one RCP in operation 1-,----------r I I! ,..._,.... I I I I I I I t ! --1 ---(750, LO) --,---i----i --l-1 ---,----+,---.--1--\.J,---r----;-r-t--,-----1------------,-,-1--.---r-1--1-i---,----,---r--l_l _______ .__. ___ r ___ l ____ tl--1--i---,----i---""'" -------------------r-----------r------------_1J __ L ----1--*----J--l--'J_l_* __ J_J __ J ___ _ 1_1 _____ 1 __________ _1 ___ 1_ ___ ,_1 ___ , ___ L __ L_J ____ _ -t[----i---=====-t l:--:H--:-:J j:=:J :i f i I ) I I ! ! I I I I I ji 11 1--r l' ! I --.---i----1 -----i---.. J ___ ,_,__,_ ____ _,_. _ _. __ i_ __ J _ _, _____ J __ , *-**---l_L __ ,_* __ L_L __ l __ * . I I . l r 1 * * ** * * * . * , r
* 1 *
* 1 , 1 ** , 1 * ,
* 1 *
* 1 * *
* l I . , I I I . , I I r r I I ! 1 1 1 1 -.-r-i---ri----1---,---,--: ---r--__ :::==-::;:=::=c--c=:i--=----=:J::::::=:i -= I l ' ! I I I I I I l ! . ' 0 500 1000 1500 2000 RCS BORON CONCENTRATION (PPM) 14A-A8 FIGURE A3 Attachment 1 to L-2016-176 Page 9 of 10 Turkey Point Unit 3 Cycle 28 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 228 216 204 192 180 168 156 ... "'O = 144 132 I/I !' 120 I/I 108 c: g 96 'iii 84 < 72 u 60 48 36 24 12 0 / / v O'S) , ... , / 0 10 Ba kC / v !/ v / v / v 20 30 j63.5, v (55. 1,212 / I/ v v (100 / /v '/ v / v / / / E ank ,,,V / / 40 50 60 70 80 90 100 Percent Reactor Power 14A-A9 
-0: w s: 0 Q. ..J ct :!: 0: w ::c I-c w I--0 ... c Q) l:? QI Q. 120 100 80 60 40 20 0 -50 FIGUREA4 Attachment 1 to L-2016-176 Page 10of10 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 3 Cycle 28 (-9100) (+6,1( 0) I \ \ I v \ -UNACI EPTABLE ur ACCEPT Al 8LE OPE RATION I/ \ (-30,50) ACCEPT'1 BLE (+, 0,50) OPERAT ON 30 10 0 10 20 30 40 50 Axial Flux Difference (%) 14A-A10    to L-2016-176 Page1of10 Revised Turkey Point Unit 4 Cycle 29 Core Operating Limits Report (COLR) 14B-A1    to L-2016-176 Page 2of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR
 
==1.0 INTRODUCTION==
This Core Operating Limits Report (COLR) for Turkey Point Unit 4 Cycle 29 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 2.1.1 2.2 2.2.1 2.3 3.1.1.1 2.4 3.1.1.2 2.5 3.1.1.3 2.6 4.1.1.3 2.7 3.1.3.2 2.8 3.1.3.6 2.9 3.2.1 2.10 3.2.2 2.11 3.2.3 2.12 3.2.5 Figure A1 A2 A3 A4 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 F0(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 29 Rod Insertion Limits vs Thermal Power Axial Flux Difference as a Function of Rated Thermal Power 14B-A1 Page 14B-A3 14B-A3-14B-A4 14B-A4 14B-A4 14B-A5 14B-A5 14B-A5 14B-A5 14B-A5 14B-A6 14B-A6 14B-A6 14B-A7 148-AS 14B-A9 14B-A10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 2.0 OPERATING LIMITS Attachment2 to L-2016-176 Page 3of10 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 NRG-approved methodologies specified in TS 6.9.1.7. 2.1 Reactor Core Safety Limits -Three Loops in Operation (TS 2.1.1) Figure A1(page14B-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 A1. 2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1) NOTE 1 on TS Table 2.2-1 Overtemperature t1 = Os, t2 = Os Lead/Lag compensator on measured T Lag compensator on measured T K1=1.31 K2 = 0.023/&deg;F t4 = 25s, ts = 3s Time constants utilized in the lead-lag compensator for Tavg Lag compensator on measured Tavg T':::;; 583.0 &deg;F Indicated Loop Tavg at RATED THERMAL POWER Ks = 0.00116/psi P' z 2235 psig Nominal RCS operating pressure f 1 = 0 for qt -qb between -18% and + 7% For each percent that the magnitude of% -qb exceeds -18%, T Trip Setpoint shall be automatically reduced by 3.51 % of its value at RA TED THERMAL POWER; and For each percent that the magnitude of qt -qb exceeds + 7%, the T Trip Setpoint shall be automatically reduced by 2.37% of its value at RATED THERMAL POWER. Where % and qb are percent RA TED THERMAL POWER in the top and bottom halves of the core respectively, and q1 + qb is total THERMAL POWER in percent of RATED THERMAL POWER. 14B-A3 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR Attachment 2 to L-2016-176 Page 4of10 NOTE 2 on TS Table 2.2-1 Overtemperature LiT (Not affected by COLR. included for completeness) The Overtemperature LiT function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% Li T span for the Li T channel, 0.2% Li T span for the Pressurizer Pressure channel, and 0.4% Li T span for the f(Lil) channel. No separate Allowable Value is provided for T avg because this function is part of the Li T value. NOTE 3 on TS Table 2.2-1 Overpower LiT Ki=1.10 Ks ;;:::: 0.0/&deg;F For increasing average temperature Ks= 0.0 For decreasing average temperature *7 ;;:::: 0 s Time constants utilized in the lead-lag compensator for T avg K6 = 0.0016/&deg;F For T > T" Ks= 0.0 For T::; T" T"::; 583.0&deg;F Indicated Loop Tavg at RATED THERMAL POWER f2 (Lil) = 0 For all Lil NOTE 4 on TS Table 2.2-1 Overpower LiT (Not affected by COLR. included for completeness) The Overpower Li T function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% Li T span for the Li T channel. No separate Allowable Value is provided for T avg because this function is part of the Li T 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% Liklk 14B-A4    to L-2016-176 Page 5of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 2.5 Moderator Temperature Coefficient (MTC) (TS 3.1.1.3) + 5.0 X 10-5 Lik/k/&deg;F From 70% RTP to 100% RTP the MTG decreasing linearly from + 5.0 X 10-5 Lik/k/&deg;F 0.0 X 10-5 Lik/k/&deg;F Less negative than -41.0 x 10-5 Lik/k/&deg;F 2.6 MTC Surveillance at 300 ppm (TS 4.1.1.3) BOL, HZP, ARO, and from HZP to 70% Rated Thermal Power (RTP) EOL, RTP, ARO Less negative than -35.0 x 10-5 Lik/k/&deg;F (-35 pcm/&deg;F) Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm. The Revised Predicted near -EOL 300 ppm MTG shall be calculated using the algorithm contained in WCAP-137 49-P-A: Revised Predicted MTG = Predicted MTG + AFD Correction -3 pcm/&deg;F If the Revised Predicted MTG is less negative than the SR 4.1.1.3.b 300 ppm surveillance limit and all the benchmark criteria contained in the surveillance procedure are met, then an MTG measurement in accordance with SR 4.1.1.3.b is not required to be performed. The neutronics methods used with WCAP-13749-P-A are those described in WCAP-11596-P-A, "Qualification of the Phoenix-Pf ANG Nuclear Design System for Pressurized Water Reactor Cores," June 1988. 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) 2.9 Axial Flux Difference (TS 3.2.1) Figure A4 (page 14B-A10) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =229 steps withdrawn. 148-AS 
'' REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 2.10 Heat Flux Hot Channel Factor Fa(Z) (TS 3.2.2) [Fo]L = 2.30 Attachment 2 to L-2016-176 Page 6of10 K(z) = 1.0 For O' .:::_ z .:::_ 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3) PFb.H = 0.3 2.12 DNB Parameters (TS 3.2.5) RCS Tavg _:::. 585.0&deg;F Pressurizer Pressure .::: 2204 psig 148-A6 t ! :I "ii 2455 psia REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR Attachment 2 to L-2016-176 Page 7 of 10 Unacceptable Operatfon Q. E GI 1-GI Cl f! GI Q. 600 ti GI .r:. .2' :I: Acceptable Operation MO;-----r----+-----t-----.,-----+-----+-------; 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 Core Power (fraction of 2644 MWt) FIGURE A1 Reactor Core Safety Limit-Three Loops in Operation 14B-A7 2 (0.0, 1.77) 1.S z z l != 0 Q ..... :::> 0 u.i Cl!. -s o.s a:: REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration Attachment 2 to L-2016-176 Page 8 of 10 I I I I ! l '. I I l 1 1 1 1 . r----, --,---------J:1=--.:--: _: MODE 4 with no RCP in operation ._I I I ' ; --------I ! I ' I l I t l I ! J -,----,--.---,----1--i----,-----.-i---r--,---. u --,:-:: ---1::J: __ ; __ ,_ . J_ _[. -] __ ---:-'l' ' I I 'I' I l I i ,-,----.----r-'----1--------,_.-i__.;J ______ I ____ _ _ u_ . ....._. __ . ___ _, ____ ._ ___ L ___ ,__J __ J ________ _ .. f 1 I
* I .. I *
* 1 I I I I. I , I t .... [ . I -,T""'"---' -----.------i---,---i--r;---.----i---,---1 ' --.-.,-,---,--l--! --l :o.----1-, MODES 1. 2. 3. and 4 with at least '-lL:--==: :-one RCP in operation 11---------
----I I l j I l ' I f I -----(750 1 0) -------.-------------:----r--,--; . 1-r-:----... i-------r----.--.-----i--1---,----,---r--i---r---.-___________________ L ____________ _i ___ _ l : I II i I I " I I j n---1-,---,-------i--i--* -,-.----1-,--,---,----,-,----i-------;--l-[-------.--:--,--------1---,----J-i-,----;--------.-----i-i---. . -!-,--:--.-, ,---,--.--(-.-,--'--i---l--1---------,---------! ! ' ' I ' f l I l I l I I 1-l .. I l '1 I I I i_I L___ ._._._ ___ r-1----..J---' ___ 1 ___ _.__,_J __ _J ____ 1 __ 1 __ I I I I 0 ........ ....................... ....... ........ .................. 0 500 1000 1500 2000 RCS BORON CONCENTRATION (PPM) 14B-A8 
.. ,-230 220 210 200 I:' 190 3: 180 "C 170 .c: .... *;: 160 II) 150 Q. Q) .... 140 .!!. c 130 0 :o::l 120 "iii 0 110 a. c;( 100 0 / V(O, 0 90 0::: 80 70 60 50 40 30 20 10 0 0 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR FIGUREA3 Attachment 2 to L-2016-176 Page 9of10 Turkey Point Unit 4 Cycle 29 Rod Insertion Limits vs Thermal Power ARO = 229 Steps Withdrawn, Overlap = 101 Steps 64.0, v (51 v v v ,V _v (100,1 f1) ... v v ... v v / v Bar kC v / v v v ... v / v ,V 105) ... v ,,V v / / v E link[ / / / / / v / / / / / {1?1 I\/ y / 10 20 30 40 50 60 70 80 90 100 Percent Reactor Pc7..wr 14B-A9 
-.-;---' 4.-1 0:: w s: 0 a. ..J ci: :i2 0:: w :i:: I-c w !;;: 0:: ... 0 ... c: Q) I:! Q) a. 120 100 80 60 40 20 0 -50 UNAC1 OPE REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR FIGUREA4 Attachment 2 to L-2016-176 Page 10of10 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 29 (*9 100) (+6,1( 0) !' \ \ I v \ ACCEPT Al !LE RATION PPERATIOll / \ (*30,50) ACCEPT A BLE (+. 0,50) OPERAT ON 30 10 0 10 20 30 40 50 Axial Flux Difference (%) 14B-A10}}

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