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{{#Wiki_filter:0 FPL.POWERING TODAY.EMPOWERING TOMORROWS Florida Power and Light Company, 9760 SW 3 4 4 th St., Homestead, FL 33035 APR 2 1 2012 L-2012-180 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 4 Docket No. 50-251 Revised Core Operating Limits Report  
{{#Wiki_filter:0 FPL.
Florida Power and Light Company, 9760 SW 34 4 th St., Homestead, FL 33035 POWERING TODAY.
EMPOWERING TOMORROWS APR 2 1 2012 L-2012-180 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re:       Turkey Point Unit 4 Docket No. 50-251 Revised Core Operating Limits Report


==Reference:==
==Reference:==
Florida Power & Light Letter 2011-118 to USNRC, dated April 11, 2011, "Core Operating Limits Report" In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4, superseding the COLR transmitted by the reference letter. This revised COLR includes additional parameters that have been relocated from the Turkey Point Technical Specifications per Amendment 243 and is applicable during Cycle 26.
Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.
Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachment cc:      Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company


Florida Power & Light Letter 2011-118 to USNRC, dated April 11, 2011,"Core Operating Limits Report" In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4, superseding the COLR transmitted by the reference letter. This revised COLR includes additional parameters that have been relocated from the Turkey Point Technical Specifications per Amendment 243 and is applicable during Cycle 26.Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.
Appendix A Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR) 14B-A1
Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company Appendix A Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR)14B-A1  


==1.0 INTRODUCTION==
==1.0     INTRODUCTION==


This Core Operating Limits Report for Turkey Point Unit 4 Cycle 26 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7.The Technical Specifications (TS) affected by this report are listed below with the section and page for each one of the TS addressed in this COLR document.Section Technical Specification Page 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 2.1.1 2.2.1 3.1.1.1 3.1.1.2 3.1.1.3 4.1.1.3 3.1.3.2 3.1.3.6 3.2.1 3.2.2 3.2.3 3.2.5 Reactor Core Safety Limits Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 Shutdown Margin Limit for MODES 1, 2, 3, 4 Shutdown Margin Limit for MODE 5 Moderator Temperature Coefficient MTC Surveillance at 300 ppm Analog Rod Position Indication System Control Rod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor FQ(Z)Nuclear Enthalpy Rise Hot Channel Factor DNB Parameters Description Reactor Core Safety Limit -Three Loops in Operation Required Shutdown Margin vs Reactor Coolant Boron Concentration Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power Axial Flux Difference as a Function of Rated Thermal Power 14B-A3 14B-A3-14B-A4 14B-A4 14B-A4 14B-A4 14B-A4 14B-A5 14B-A5 14B-A5 14B-A5 14B-A5 14B-A5 14B-A6 14B-A7 14B-A8 14B-A9 Figure Al A2 A3 A4 14B-A2  
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


===2.0 OPERATING===
2.0  OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in the Introduction are presented below and listed sequentially by Technical Specification (TS). These limits have been developed using the NRC-approved methodologies specified in TS 6.9.1.7.
2.1  Reactor Core Safety Limits - Three Loops in Operation (TS 2.1.1)
          -  Figure Al (page  14B-A6)    In Modes 1 and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure Al.
2.2  Reactor Trip System Instrumentation Setpoints (TS 2.2.1)
NOTE 1 on TS Table 2.2-1 OvertemDerature AT
            -  T1I=OS, T2 =OS            Lead/Lag compensator on measured AT
            -  T3 =Os                    Lag compensator on measured AT
            -  K, =1.24
            -  K 2 =0.0171 0 F
            -  T4 =25s,t 5,= 3s          Time constants utilized in the lead-lag compensator for Tavg
            -  T6 =0O                    Lag compensator on measured      Tavg
            -  T'*!g577.2 OF            Nominal Tavg at RATED THERMAL POWER
            -  K3 = 0.0l/PSig P' >_2235 psig            Nominal RCS operating pressure
            -  f1(AI) = 0 for qt - qb between - 50% and + 2%.
For each percent that the magnitude of qt -            qb  exceeds - 50%,
the AT Trip Setpoint shall be automatically reduced by 0.0%
of its value at RATED THERMAL POWER; and For each percent that the magnitude of qt - qb exceeds + 2%,
the AT Trip Setpoint shall be automatically reduced by 2.19%
of its value at RATED THERMAL POWER.
Where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER.
14B-A3


LIMITS The cycle-specific parameter limits for the specifications listed in the Introduction are presented below and listed sequentially by Technical Specification (TS). These limits have been developed using the NRC-approved methodologies specified in TS 6.9.1.7.2.1 Reactor Core Safety Limits -Three Loops in Operation (TS 2.1.1)-Figure Al (page 14B-A6)In Modes 1 and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure Al.2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1)NOTE 1 on TS Table 2.2-1 OvertemDerature AT-T1I=OS, T2 =OS-T3 =Os-K, =1.24-K 2 =0.0171 0 F-T4 =25s,t 5 ,= 3s-T6 =0O-T'!g577.2 OF-K 3= 0.0l/PSig Lead/Lag compensator on measured AT Lag compensator on measured AT Time constants utilized in the lead-lag compensator for Tavg Lag compensator on measured Tavg Nominal Tavg at RATED THERMAL POWER P' >_ 2235 psig Nominal RCS operating pressure-f 1 (AI) = 0 for qt -qb between -50% and + 2%.For each percent that the magnitude of qt -qb exceeds -50%, the AT Trip Setpoint shall be automatically reduced by 0.0%of its value at RATED THERMAL POWER; and For each percent that the magnitude of qt -qb exceeds + 2%, the AT Trip Setpoint shall be automatically reduced by 2.19%of its value at RATED THERMAL POWER.Where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER.14B-A3 NOTE 3 on TS Table 2.2-1 Overpower AT-1(45 1.10-Ks5 -0.021°F For increasing average temperature
NOTE 3 on TS Table 2.2-1 Overpower AT
-K5 = 0.0 For decreasing average temperature
        - 1(45 1.10
-T 7 > 10 S Time constants utilized in the lead-lag compensator for Tavg-K 6 = 0.001 61&deg;F For T > T"-K 6 = 0.0 For T < T"-T" _ 577.2 0 F Nominal Tavg at RATED THERMAL POWER-f 2 (Al) = 0 For all Al 2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1.1)-Figure A2 (page 14B-A7)2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)-> 1% Ak/k 2.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)-< + 5.0 x 10- Ak/k/OF BOL, HZP, ARO and from HZP to 70% Rated Thermal Power (RTP)-From 70% RTP to 100% RTP the MTC decreasing linearly from < + 5.0 x 10s Ak/k/&deg;F to < 0.0 x 10 5 Ak/k/&deg;F-Less negative than -35.0 x 10 5 AkIk/0 F EOL, RTP, ARO 2.6 Moderator temperature coefficient (MTC) Surveillance at 300 ppm (TS 4.1.1.3)Less negative than -30.0 x 10s Ak/k/&deg;F Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.14B-A4  
        - Ks5 - 0.021&deg;F           For increasing average temperature
        - K5 = 0.0               For decreasing average temperature
        - T7  > 10 S             Time constants utilized in the lead-lag compensator for Tavg
        - K6 = 0.001 61&deg;F         For T > T"
        - K 6 = 0.0               For T < T"
        - T" _ 577.2 0 F         Nominal Tavg at RATED THERMAL POWER
        - f 2 (Al) = 0           For all Al 2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1.1)
    - Figure A2 (page 14B-A7) 2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)
        - > 1% Ak/k 2.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)
        - < + 5.0 x 10- Ak/k/OF                                     BOL, HZP, ARO and from HZP to 70% Rated Thermal Power (RTP)
        - From 70% RTP to 100% RTP the MTC decreasing linearly from < + 5.0 x 10s Ak/k/&deg;F to < 0.0 x 10 5 Ak/k/&deg;F
        - Less negative than - 35.0 x 10 5 AkIk/ 0 F               EOL, RTP, ARO 2.6 Moderator temperature coefficient (MTC) Surveillance at 300 ppm (TS 4.1.1.3)
Less negative than - 30.0 x 10s Ak/k/&deg;F                   Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.
14B-A4


===2.7 Analog===
2.7 Analog Rod Position Indication System (TS 3.1.3.2)
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.
      -   Figure A3 (page 14B-A8)   The All Rods Out (ARO) position for all shutdown Banks and Control Banks is defined to be 228 steps withdrawn.
2.8  Control Rod Insertion Limits (TS 3.1.3.6)
      -  Figure A3 (page 14B-A8)  The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =228 steps withdrawn.
2.9  Axial Flux Difference (TS 3.2.1)
      -  Figure A4 (page 14B-A9) 2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)
          -  [FQ]L = 2.50
          -  K(z) =1.0              For 0' < z < 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)
          -  FAHRTP = 1.70
          -  PFAH  = 0.3 2.12 DNB Parameters (TS 3.2.5)
          -  RCS Tavg < 581.2 &deg;F
          -  Pressurizer Pressure > 2200 psig 14B-A5


===2.8 Control===
680 670 psia
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.
      '660-2455 660                                      I          UNACCEPTABLE 5 0                                            OPERATION 2250 psia
* 640
%a630      -
t2000        psia 620 I--
610  -1805 Psia-                            1 600 ACCEPTABLE\
590        OPERATION          -
580V 570 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 Power (fraction of nominal)
FIGURE Al Reactor Core Safety Limit - Three Loops in Operation 14B-A6


===2.9 Axial===
2.0 (0..O1 .77) 1.5 I A I ACCEPTABLE OPERATION:
Flux Difference (TS 3.2.1)-Figure A4 (page 14B-A9)2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)-[FQ]L = 2.50-K(z) =1.0 For 0' < z < 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)-FAHRTP = 1.70-PFAH = 0.3 2.12 DNB Parameters (TS 3.2.5)-RCS Tavg < 581.2 &deg;F-Pressurizer Pressure > 2200 psig 14B-A5 680 670'660-2455 psia 660 I UNACCEPTABLE 5 0 OPERATION 2250 psia 640%a 630 -t2000 psia 620 I--610 -1805 Psia- 1 600 ACCEPTABLE\
I I I I III I If I I I I I I I I I I I I I I I J i- i-I l l I I I 1 1 1 1 H t -
590 OPERATION
z                                                                        1 1 1 11 H IM       1 '1111       1 11 if ;III 1.0 I I I I fi ll1                            11 11i ll fi ll I III I 111H                            1 1 if HIM. HIM               III If    11    1                   111 11     H ill If 0.5
-580V 570 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 Power (fraction of nominal)FIGURE Al Reactor Core Safety Limit -Three Loops in Operation 14B-A6 2.0 (0..O1 .77)z 1.5 I A I ACCEPTABLE OPERATION:
                          .. .~~50
I I I I III I If I I I I I I H t -I I I I I I I I I J i- i-I l l I I I 1 1 1 1 1 1 1 1 1 H IM 1 '1111 1 11 i f ; I I I 1 1 1 1 i l l f i l l I I I I I I I I f i l l 1 1 1 i f I 111H HIM. HIM III I f 1 1 1 1 11 1 1 H i l l If 1.0 0.5..~~50 .......0.. ......0. ..0.0 0 500 1000 1500 2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7 FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 230 __ __ __220 _63.52 210_ (5 X.212 ?2U 200 -.190 180 Batk C 170 _ _La 160 ____ _S150o- -140- -_u, 130 /2 120 ___11o _- , o0 100 -90 I80 -/ -.....'nk3 70 __ix 60 -50 40 __30 /20 /10 1 ._0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A8 FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120-(-l1)100)  
                                      . .0..         . . . . ..         0. . .
(+7,10)100 60 80__1-
0.0 0           500             1000           1500           2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7
/ I.IACCEPELE OPERATIN('U 640 J -o ) ACCEPTABLE 00660) OEAON kS))C 20 0--50 30 10 0 10 20 30 40 50 Aial Rx ifference (9/1 14B-A9}}
 
FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 230                               __       __         __
220                                          _63.52 210_                                               X.212 (5 ?2U 200
  .190     -
180                           Batk C 170                                         _          _
La  160                                   ____               _
S150o-                 -
140-   -_
u, 130               /
2   120                   ___
11o      ,            _-
o0100 -
90           I
  *j 80 -/ -.....                                                       'nk3 ix 70 60 -                             __
50 40                             __
30                              /
20                         /
10               1 .         _
0        10           20       30         40         50     60   70 80 90 100 Percent Reactor Power 14B-A8
 
FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120-(-l1)100)       (+7,10) 100 UINAM*FTABLE /
* I.IACCEPELE 1-6080__
O*PERA'TION                                                          OPERATIN(
640
'U J -o )               ACCEPTABLE 00660)         OEAON             (+2* kS))
C   20 0-
        -50     -40      -30       -20        -10       0         10   20       30       40 50 Aial Rxifference (9/1 14B-A9}}

Latest revision as of 16:28, 6 February 2020

Revised Core Operating Limits Report
ML12130A205
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 04/21/2012
From: Kiley M
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2012-180
Download: ML12130A205 (10)
v • d • e


Text

0 FPL.

Florida Power and Light Company, 9760 SW 34 4 th St., Homestead, FL 33035 POWERING TODAY.

EMPOWERING TOMORROWS APR 2 1 2012 L-2012-180 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 4 Docket No. 50-251 Revised Core Operating Limits Report

Reference:

Florida Power & Light Letter 2011-118 to USNRC, dated April 11, 2011, "Core Operating Limits Report" In accordance with Technical Specification 6.9.1.7, the attached revised Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4, superseding the COLR transmitted by the reference letter. This revised COLR includes additional parameters that have been relocated from the Turkey Point Technical Specifications per Amendment 243 and is applicable during Cycle 26.

Should there be any questions, please contact Robert Tomonto, Licensing Manager, at 305-246-7327.

Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company

Appendix A Turkey Point Unit 4 Cycle 26 Core Operating Limits Report (COLR) 14B-A1

1.0 INTRODUCTION

This Core Operating Limits Report for Turkey Point Unit 4 Cycle 26 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7.

The Technical Specifications (TS) affected by this report are listed below with the section and page for each one of the TS addressed in this COLR document.

Section Technical Specification Page 2.1 2.1.1 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

2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in the Introduction are presented below and listed sequentially by Technical Specification (TS). These limits have been developed using the NRC-approved methodologies specified in TS 6.9.1.7.

2.1 Reactor Core Safety Limits - Three Loops in Operation (TS 2.1.1)

- Figure Al (page 14B-A6) In Modes 1 and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure Al.

2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1)

NOTE 1 on TS Table 2.2-1 OvertemDerature AT

- T1I=OS, T2 =OS Lead/Lag compensator on measured AT

- T3 =Os Lag compensator on measured AT

- K, =1.24

- K 2 =0.0171 0 F

- T4 =25s,t 5,= 3s Time constants utilized in the lead-lag compensator for Tavg

- T6 =0O Lag compensator on measured Tavg

- T'*!g577.2 OF Nominal Tavg at RATED THERMAL POWER

- K3 = 0.0l/PSig P' >_2235 psig Nominal RCS operating pressure

- f1(AI) = 0 for qt - qb between - 50% and + 2%.

For each percent that the magnitude of qt - qb exceeds - 50%,

the AT Trip Setpoint shall be automatically reduced by 0.0%

of its value at RATED THERMAL POWER; and For each percent that the magnitude of qt - qb exceeds + 2%,

the AT Trip Setpoint shall be automatically reduced by 2.19%

of its value at RATED THERMAL POWER.

Where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER.

14B-A3

NOTE 3 on TS Table 2.2-1 Overpower AT

- 1(45 1.10

- Ks5 - 0.021°F For increasing average temperature

- K5 = 0.0 For decreasing average temperature

- T7 > 10 S Time constants utilized in the lead-lag compensator for Tavg

- K6 = 0.001 61°F For T > T"

- K 6 = 0.0 For T < T"

- T" _ 577.2 0 F Nominal Tavg at RATED THERMAL POWER

- f 2 (Al) = 0 For all Al 2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1.1)

- Figure A2 (page 14B-A7) 2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)

- > 1% Ak/k 2.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)

- < + 5.0 x 10- Ak/k/OF BOL, HZP, ARO and from HZP to 70% Rated Thermal Power (RTP)

- From 70% RTP to 100% RTP the MTC decreasing linearly from < + 5.0 x 10s Ak/k/°F to < 0.0 x 10 5 Ak/k/°F

- Less negative than - 35.0 x 10 5 AkIk/ 0 F EOL, RTP, ARO 2.6 Moderator temperature coefficient (MTC) Surveillance at 300 ppm (TS 4.1.1.3)

Less negative than - 30.0 x 10s Ak/k/°F Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.

14B-A4

2.7 Analog Rod Position Indication System (TS 3.1.3.2)

- Figure A3 (page 14B-A8) The All Rods Out (ARO) position for all shutdown Banks and Control Banks is defined to be 228 steps withdrawn.

2.8 Control Rod Insertion Limits (TS 3.1.3.6)

- Figure A3 (page 14B-A8) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =228 steps withdrawn.

2.9 Axial Flux Difference (TS 3.2.1)

- Figure A4 (page 14B-A9) 2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)

- [FQ]L = 2.50

- K(z) =1.0 For 0' < z < 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)

- FAHRTP = 1.70

- PFAH = 0.3 2.12 DNB Parameters (TS 3.2.5)

- RCS Tavg < 581.2 °F

- Pressurizer Pressure > 2200 psig 14B-A5

680 670 psia

'660-2455 660 I UNACCEPTABLE 5 0 OPERATION 2250 psia

  • 640

%a630 -

t2000 psia 620 I--

610 -1805 Psia- 1 600 ACCEPTABLE\

590 OPERATION -

580V 570 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 Power (fraction of nominal)

FIGURE Al Reactor Core Safety Limit - Three Loops in Operation 14B-A6

2.0 (0..O1 .77) 1.5 I A I ACCEPTABLE OPERATION:

I I I I III I If I I I I I I I I I I I I I I I J i- i-I l l I I I 1 1 1 1 H t -

z 1 1 1 11 H IM 1 '1111 1 11 if ;III 1.0 I I I I fi ll1 11 11i ll fi ll I III I 111H 1 1 if HIM. HIM III If 11 1 111 11 H ill If 0.5

.. .~~50

. .0.. . . . . .. 0. . .

0.0 0 500 1000 1500 2000 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A7

FIGURE A3 Turkey Point Unit 4 Cycle 26 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withdrawn, Overlap = 100 Steps 230 __ __ __

220 _63.52 210_ X.212 (5 ?2U 200

.190 -

180 Batk C 170 _ _

La 160 ____ _

S150o- -

140- -_

u, 130 /

2 120 ___

11o , _-

o0100 -

90 I

  • j 80 -/ -..... 'nk3 ix 70 60 - __

50 40 __

30 /

20 /

10 1 . _

0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A8

FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 26 120-(-l1)100) (+7,10) 100 UINAM*FTABLE /

  • I.IACCEPELE 1-6080__

O*PERA'TION OPERATIN(

640

'U J -o ) ACCEPTABLE 00660) OEAON (+2* kS))

C 20 0-

-50 -40 -30 -20 -10 0 10 20 30 40 50 Aial Rxifference (9/1 14B-A9

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