View source for L-2013-034, Core Operating Limits Report for Unit 4 Cycle 27

{{Adams
| number = ML13042A222
| issue date = 01/28/2013
| title = Core Operating Limits Report for Unit 4 Cycle 27
| author name = Kiley M
| author affiliation = Florida Power &amp; Light Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000251
| license number = 
| contact person = 
| case reference number = L-2013-034
| document type = Fuel Cycle Reload Report, Letter type:L
| page count = 11
}}

=Text=
{{#Wiki_filter: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/&deg;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/&deg;F to < 0.0 x 10.5 Ak/k/&deg;F
           -  Less negative than - 41.0 x 10-5 Ak/k/&deg;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/&deg;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.&#xfd;                               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}}