L-2024-175, Cycle 34 Core Operating Report
| ML24298A061 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/24/2024 |
| From: | Mack K Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-2024-175 | |
| Download: ML24298A061 (1) | |
Text
October 24, 2024
U.S. Nuclear Regulatory Commission ATTN : Document Cont rol Desk Washington, DC 20555- 00001
Re : Florida Power & Light Company Turkey Point Nuclear Plant, Unit 3 Docket Nos. 50-250
Turkey Point Unit 3 Cycle 34 Core Operating Limits Report
Pursuant to Turkey Point Technical Specification (TS) 5.6.3, Flor ida Power & Light Company (FPL) is submitting the Unit 3 Core Operating Limits Report (COLR) for operating Cycle 34.
This letter contains no new regulatory commitments.
If you have any questions regarding this submittal, please contact Maribel Valdez, Fleet Licensing Manager, at 561-904 - 5164.
Sincerely, K~i;.;~
Director, Licensing and Regulatory Compliance
Attachment:
Turkey Point Unit 3 Cycle 34 Core Operating Limits Report
cc : Regional Administrator, Region II, USNRC Project Manager, Turkey Point Nuclear Generating Station, USNRC Resident Inspector, Turkey Point Nuclear Generating Station, USNRC
Florida Power & Light Company
97 60 SW 344th Street, Homestead, FL 33035 Turkey Point Nuclear Plant L-2024-175 Docket Nos. 50-250 and 50-251 Attachment
Turkey Point Unit 3 Cycle 34 Core Operating Limits Report
(11 pages follow)
Turkey Point Unit 3 Cycle 34 I~
Core Operating Limits Report (COLR)
1.0 INTRODUCTION
This Core Operating Limits Report for Turkey Point Unit 3 Cycle 34 has been prepared in accordance ~
with the requirements of Technical Specification 5.6.3.
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 Sls 14A-A3 2.2 3.3.1 Reactor Trip System (RTS) Instrumentation 14A-A3-14A-A4 2.3 3.1.1 Shutdown Margin (SOM) Limit for MODES 1, 2, 3, 4 14A-A4 3.1.4 14A-A4 3.1.5 14A-A4 3.1.6 14A-A4 3.1.8 14A-A4 2.4 3.1.1 Shutdown Margin (SOM) Limit for MODE 5 14A-A4 2.5 3.1.3 Moderator Temperature Coefficient (MTC) 14A-A5 2.6 3.1.3 MTC Surveillance at EOC 14A-A5 2.7 3.1.7 Rod Position Indication 14A-A5 2.8 3.1.6 Control Bank Insertion Limits 14A-A5a 2.9 3.2.3 Axial Flux Difference (AFD) 14A-A5a ~
2.10 3.2.1 Heat Flux Hot Channel Factor (Fo(Z)) 14A-A6 2.11 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN.c\\H) 14A-A6c 2.12 3.4.1 RCS Pressure, Temperature, and Flow Departure 14A-A6c from Nucleate Boiling (DNB) Limits 2.13 3.1.5 Shutdown Bank Insertion Limits 14A-A6c 2.14 3.9.1 Boron Concentration MODE 6 14A-A6c 2.15 Peaking Factor Limit Report 14A-A6c
Figure Description A1 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 34 Rod Insertion Limits vs Thermal Power 14A-A9 K0 A4 Axial Flux Difference as a Function of Rated Thermal Power 14A-A10
14A-A2 Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
2.0 Operating Limits
The cycle-specific parameter limits for the specifications listed in the Introduction are presented below and listed by Technical Specification (TS). These limits have been developed using the NRG-approved methodologies specified in TS 5.6.3.
2.1 Reactor Core SLs (TS 2.1.1)
- Figure A1 (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 A1.
2.2 Reactor Trip System (RTS) Instrumentation (TS 3.3.1)
NOTE 1 on TS Table 3.3.1-1 Overtemperature !lT
- 't1 = Os, 't2 = Os Lead/Lag compensator on measured L'l T
- 't3 = 2s Lag compensator on measured L'l T
- K1 = 1.31
- K2 = 0.023/°F
- 't4 = 25s, 'ts= 3s Time constants utilized in the lead-lag compensator for Tavg
- 'ts= 2s Lag compensator on measured Tav9
- T' :s; 583.0 °F Indicated Loop Tavg at RATED THERMAL POWER
- K3 = 0.00116/psi
- P' ~ 2235 psig Nominal RCS operating pressure
- f1(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 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 Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 I<§>
Core Operating Limits Report (COLR)
NOTE 2 on TS Table 3.3.1-1 Overpower LlT
- K4 = 1.09
- Ks~ 0.0/°F For increasing average temperature
- Ks= 0.0/°F For decreasing average temperature
- 't7 ~ 0 s Time constants utilized in the lead-lag compensator for T avg
- Ke= 0.0016/°F For T > T"
- Ke= 0.0 For Ts T"
- T" ~ 583.0°F Indicated Loop Tav9 at RATED THERMAL POWER
- f2 (~I)= 0 For all ~I
2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, and TS 3.1.8)
- Figure A2 (page 14A-A8)
2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1)
- ;:: 1.77% Ak/k
14A-A4 Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
2.5 Moderator temperature coefficient (MTC) (TS 3.1.3)
- S+ 5.0 x 10-5 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/°F
- Less negative than - 41.0 x 10*5 Ak/k/°F EOL, RTP, ARO
2.6 MTC Surveillance at EOC (TS 3.1.3)
- Less negative than - 35.0 x 10-5 Ak/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-137 49-P-A:
Revised predicted MTC = Predicted MTC + AFD Correction - 3 pcm/°F If the Revised Predicted MTC is less negative than the SR 3.1. 3.2 300 ppm surveillance limit and all the benchmark criteria contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 3.1.3.2 is not required to be performed.
The neutronics methods used with WCAP-13749-P-A are those described in WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport CODE PARAGON,"
August 2004.
The benchmark criteria referenced in SR 3.1.3.2 are contained in WCAP-13749-P-A.
In the event that the 300 ppm Surveillance fails to be less negative than the limit, SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of::; 60 ppm is less negative than:
-39.8 x 10-5 L\\k/k/°F (-39.8 pcm/°F) r
2.7 Rod Position Indication (TS 3.1.7)
- Not Used
14A-A5 Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
2.8 Control Bank Insertion Limits (TS 3.1.6)
- Figure A3 (page 14A-A9) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO
=230 steps withdrawn.
2.9 Axial Flux Difference (AFD) (TS 3.2.3)
- Figure A4 (page 14A-A10) or, within a + /- 2% or + /- 3%
target band about the target flux difference during Base Load operation.
- PT= Reactor Power at which predicted FQ would exceed its limit (consistent with SR 3.2.1.2).
14A-A5a Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
2.10 Heat Flux Hot Channel Factor Fo(Z) (TS 3.2.1)
FoL(Z) is the Fo limit at RATED THERMAL POWER and shall be limited by the following relationships:
- [Fo]M(Z) S [Fif x [K(Z)J for P > 0.5
- [F 0 ]M(Z) S [FQf 0.5 x [K(Z)J for P S 0.5
where:
_ p = Thermal Power Rated Thermal Power
- [Fo]M =The Measured Value,
- [FQ]L = 2.40
- K(z) = 1.0 For O' :5 z :5 12' where z is core height in ft
NOTES------------------------------------------------------
- 1. [Fo]P = Predicted Fo, as predicted by approved physics calculations.
- 2. Pr= Reactor power level at which [Fo]P would exceed its limits, [Fo]L/[Fo]P.
- 3. Fi(Z) is the normalized axial power distribution from thimble j at core elevation (Z)
- 4. PRs = minimum value of the ratio of [F5 Z)]/[Fo(Z)]Rs Meas.
- 5. [Fo(Z)]RB Meas. =[Fxy(Z)]Map Meas. X Fz(Z) X 1.09
- 6. [F5 (Z)J = [F5] x K(Z).
Fo(Z) shall be evaluated to determine if Fo(Z) is within its limit as follows:
- a. Increase the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
- b. Verify F~(Z) :5 F5( (Z)
Where F~(Z) is the measured Fo(Z) increased by the allowance for manufacturing tolerances and measurement uncertainty and F5 (Z) is the Fo limit.
- c. With the relationship specified in b. above not being satisfied:
- 1) Calculate the percent F~ (Z) exceeds its limit by the following expression:
(( :~(z) ]-1]x100 for P;;:: 0.5
[Fol x K(Z)/P
(( [Fol x :~<z) ]-1]x100forP<0.5 K(Z)to.s
- 2) The following action shall be taken:
a) Comply with the requirements of Specification 3.2.1 for F~(Z) exceeding its limit by the percent calculated above.
14A-A6 Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
SR 3.2.1.2 MIDS MIDS Operation is permitted at power above PT where PT equals the ratio of [Fo]L divided by [Fo]P if the following Augmented Surveillance (Movable lncore Detection System, MIDS) requirements are satisfied.
- a. The axial power distribution shall be measured by MIDS when required such that the limit of [Fojl/P times K(Z) is not exceeded.
- 1. At least two thimbles available for which Ri and ai as defined in TS 3.2.1 Bases have been determined.
- 2. At least two movable detectors available for mapping Fi(Z).
- 3. The continued accuracy and representativeness of the selected thimbles shall be verified by using the most recent flux map to update the R for each selected thimble. The flux map must be updated at least once per 31 effective full power days.
where:
R = Total peaking factor from a full flux map ratioed to the axial peaking factor in a selected thimble.
j = The thimble location selected for monitoring.
Base Load Base Load operation is permitted at powers above PT if the following requirements are satisfied:
- a. Either of the following preconditions for Base Load operation must be satisfied.
- 1. For entering Base Load operation with power less than PT, a) Maintain THERMAL POWER between PT/1.05 and PT for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Maintain the AFD (Delta-I) within a+/- 2% or+/- 3% target band for at least 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> per 24-hour period.
c) After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> have elapsed after entering base load operation, take a full core flux map to determine F~(Z) unless a valid full core flux map was taken within the time period in SR 3.2.1.1.
d) Calculate PsL per Section b.3 (see next page).
- 2. For entering Base Load operation with power greater than PT, a) Maintain THERMAL POWER between PT and the power limit determined in MIDS operation for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and maintain Augmented Surveillance requirements of MIDS operation during this period.
b) Maintain the AFD (Delta-I) within a+/- 2% or+/- 3% target band for at least 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> per 24-hour period, c) Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering base load operation take a full core flux map to determine F~(Z) unless a valid full core flux map was taken within the time period specified in SR 3.2.1.1.
d) Calculate PsL per Section b.3 (see below).
14A-A6a Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
- b. Base Load operation is permitted provided:
- 1. THERMAL POWER is maintained between Pr and PsL or between Pr and 100%
(whichever is most limiting).
- 2. AFD (Delta-I) is maintained within a +/- 2% or+/- 3% target band.
- 3. Full core flux maps are taken at least once per 31 effective full power days.
PsL and Pr are defined as:
L PsL = [Fol xK(Z)
F~(Z)xW(z)BLx1.09 Pr= [Fafl[Fat where: F~(z) is the measured FQ(Z) with no allowance for manufacturing tolerances or measurement uncertainty. For the purpose of this Specification [F~(z)] shall be obtained between elevations bounded by 10% and 90% of the active core height. is the cycle
[Fo]L is the Fo limit. K(z) is given in the COLR Section 2.10. W(z)sL dependent function that accounts for limited power distribution transients encountered during Base Load operation. The W(z)sL function is given as per Peaking Factor Limit Report, COLR Section 2.15. The 9% uncertainty factor accounts for manufacturing tolerance, measurement error, rod bow and any burnup and power dependent peaking factor increases.
- c. During Base Load operation, if the THERMAL Power is decreased below Pr, then the preconditions for Base Load operation in Step a. above shall be satisfied before re-entering Base Load operation.
Radial Burndown
Radial Burndown operation is permitted at powers above Pr if the following Radial Burndown conditions are satisfied:
- a. Radial Burndown operation is restricted to use at powers between Pr and PRs or Pr and 1.00 (whichever is most limiting). The maximum relative power permitted under Radial Burndown operation, PRs, is equal to minimum value of the ratio of [F5 Z)]/[Fo (Z)]Rs Meas.
where: [Fo(Z)]RB Meas. =[Fxy(Z)]Map Meas. x Fz(Z) x 1.09 and
[F5 Z] is equal to [F5] x K(Z).
- b. A full core flux map to determine [Fxy(Z)]Map Meas. shall be taken in accordance with in the SFCP for SR 3.2.1.1. For the purpose of the specification, [Fxy(Z)]Map Meas. shall be obtained between the elevations bounded by 10% and 90% of the active core height.
- c. The function Fz(Z), provided in the Peaking Factor Limit Report (COLR Section 2.15), is determined analytically and accounts for the most perturbed axial power shapes which can occur under axial power distribution control. The uncertainty factor of 9% accounts for manufacturing tolerances, measurement error, rod bow, and any burnup dependent peaking factor increases.
- d. Radial Burndown operation may be utilized at powers between Pr and PRs, or Pr and 1.00 (whichever is most limiting) provided that the AFD (Delta-I) is within +/- 5% of the target axial offset.
14A-A6b Revised 11/11/2025 Turkey Point Unit 3 Cycle 34 Core Operating Limits Report (COLR)
2.11 Nuclear Enthalpy Rise Hot Channel Factor (FN!iH) (TS 3.2.2)
- FN!iH :s; Ft,HRrP[1.0 + PF!iH(1-P)]
Where:
F liHRrP = 1.650 PF!iH = 0.3
- F!iHRrP = FiiH limit at RTP
- PF"H = Power Factor Multiplier for F!iH
_ p = Thermal Power Rated Thermal Power
2.12 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1)
- RCS Tavg :5 585.0 °F
- Pressurizer Pressure~ 2204 psig
- RCS total flow rate ~ 270,000 gpm
2.13 Shutdown Bank Insertion Limit (TS 3.1.5)
- The Shutdown Banks shall be limited in physical insertion to ARO position.
2.14 Boron Concentration MODE 6 (TS 3.9.1)
The boron concentration of the Reactor Coolant System (RCS), the refueling canal, and the refueling cavity shall be maintained to ensure that the more restrictive of the following reactivity conditions is met; either:
- a. A Keff of:::; 0.95, or,
- b. A boron concentration of:::: 2300 ppm.
2.15 Peaking Factors Limit Report The W(z) function(s) for Base Load Operation corresponding to a+/- 2% band about the target flux difference and/or a+/- 3% band about the target flux difference, the Load-Follow function Fz(z) and the augmented surveillance turnon power fraction PT shall be provided to the U.S. Nuclear Regulatory Commission, whenever Pr is< 1.0. In the event, the option of Base Load Operation will not be exercised, the submission of the W(z) function is not required. Should these values (i.e., W(z), Fz(z) and Pr) change requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC Document Control desk with copies to the Regional Administrator and the Resident Inspector within 30 days of their implementation, unless otherwise approved by the Commission.
The analytical methods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and submitted to the NRC for review and approval prior to their use if the change is determined to require NRC approval in accordance with 10 CFR 50.59 or if such the change would require a change to the Technical Specifications.
14A-A6c Revised 11/11/2025 FIGURE A3
Turkey Point Unit 3 Cycle 34 Rod Insertion Limits vs Thermal Power ARO = 230 Steps Withdrawn, Overlap = 102 Steps
230 L/ 64 5 230. '
220.,,, I I 210.,,, 55.2, 212 200.,,,
190.,,,
180.,, 100, 17~
170,,.,
c 160,,., :,'
~ 150,.,,-RankC Jill'
,a 140 ~' Jill'
- i 130
~,- Jill'
'i 120 !. 110,,.,,.......,,,.,
.el 100 -0, 105,.
..!!!. 90,.
- i:::i 6 80.........- BankD
'iii 70.,,,i.,-
£ 60,.,i.,-
< 50 ~'
0 40,.,,
~ 30
~....
20,.,,....
10 12, 0.,....
I.J 0
0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power
14A-A9 Revised 11/11/2025 FIGURE A4
Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 3 Cycle 34 1<0
120
100 (-9,100' (+7,100
~
0: [\\
w / \\
s: 80 0 / \\
n.
.J UI IACCEPTAI llLE
<( UNAC CEPTABLE /
- !: OPE RATION ::>PERATIOfJ 0:
w 60 i!:
C I/ \\
w ACCEPTJ IBLE I- (-30,50) OPERAT ON (+20,50)
~
.... 0 40
... C G)
E G) n.
20
0
-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference(%)
14A-A10 Revised 11/11/2025