Text

Cycle 34 Core Operating Limits Report
	ML24122C677
Person / Time
Site:	Turkey Point
Issue date:	05/01/2024
From:	Rasmus P; Florida Power & Light Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	L-2024-073
	Download: ML24122C677 (1)
	v • d • e

May 1, 2024 L-2024-073 10 CFR 50.36

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-00001

Re: Turkey Point Nuclear Plant, Unit 4 Docket 50-251 Cycle 34 Core Operating Limits Report

Pursuant to Turkey Point Unit 4 Technical Specification (TS) 5.6.3, Florida Power & Light Company (FPL) is submitting the Core Operating Limits Report (COLR) for Cycle 34. This revision reflects changes from Current Technical Specifications (CTS) to Improved Technical Specifications (ITS).

Should you have any questions regarding this submission, please contact Mr. Kenneth Mack, Fleet Licensing Manager, at 561-904-3635.

Sincerely, r{~

Paul Rasmus General Manager, Regulatory Affairs Florida Power & Light Company

Enclosure Turkey Point Unit 4, Cycle 34 Core Operating Limits Report

cc: USNRC Regional Administrator, Region 11 USNRC Project Manager, Turkey Point Nuclear Plant USNRC Resident Inspector, Turkey Point Nuclear Plant

Florida Power & Light Company

9760 SW 344th Street, Homestead, FL 33035

Enclosure:

Turkey Point Unit 4, Cycle 34 Core Operating Limits Report

( 8 pages follow)

Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

1.0 Introduction

This Core Operating Limits Report for Turkey Point Unit 4 Cycle 34 has been prepared in accordance with the I@)

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 14B-A3 @)

2.2 3.3.1 Reactor Trip System (RTS) Instrumentation 14B-A3-14B-A4 2.3 3.1.1 Shutdown Margin (SOM) Limit for MODES 1, 2, 3, 4 14B-A4 3.1.4 14B-A4 3.1.5 14B-A4 3.1.6 14B-A4 3.1.8 14B-A4 2.4 3.1.1 Shutdown Margin (SOM) Limit for MOOE 5 14B-A4 2.5 3.1.3 Moderator Temperature Coefficient (MTC) 14B-A5 2.6 3.1.3 MTC Surveillance at EOC 14B-A5 2.7 3.1.7 Rod Position Indication 14B-A5 2.8 3.1.6 Control Bank Insertion Limits 14B-A5 2.9 3.2.3 Axial Flux Difference (AFD) 14B-A5 2.10 3.2.1 Heat Flux Hot Channel Factor (Fo(Z)) 14B-A6 2.11 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNLiH) 14B-A6c 2.12 3.4.1 RCS Pressure, Temperature, and Flow Departure 14B-A6c from Nucleate Boiling (DNB) Limits 2.13 3.1.5 Shutdown Bank Insertion Limits 14B-A6c 2.14 3.9.1 Boron Concentration MODE 6 14B-A6c 2.15 Peaking Factor Limit Report 14B-A6c

Figure Description A1 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 34 Rod Insertion Limits vs Thermal Power 14B-A9 @

A4 Axial Flux Difference as a Function of Rated Thermal Power 14B-A10

14B-A2 Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

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 I~

specified in TS 5.6.3. ~

2.1 Reactor Core SLs (TS 2.1.1)

Figure A1(page 148-A?) 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 (RTS) Instrumentation (TS 3.3.1)

NOTE 1 on TS Table 3.3.1-1 Overtemperature LlT

't'1 = Os, 't'2 = Os Lead/Lag compensator on measured Ll T

't'3 = 2s Lag compensator on measured Ll T K1 = 1.31 K2 = 0.023/°F

't'4 = 25s, 't's = 3s Time constants utilized in the lead-lag compensator for T avg

't'6 = 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(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 Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

NOTE 2 on TS Table 3.3.1-1 Overpower Ll T 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 Tavg KG= 0.0016/°F For T > T" KG= 0.0 ForT ~ T" Indicated Loop Tavg at RATED THERMAL POWER fa (Al)= 0 For all Lll

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, TS 3.1.8)

Figure A2 (page 14B-A8)

2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1)

~ 1.77 % Ak/k

14B-A4 Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

2.5 Moderator temperature coefficient (MTC) (TS 3.1.3)

~ + 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 I accordance with SR 3.1.3.2 is not required to be performed.

The neutronics methods used with WCAP-137 49-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

2.7 Rod Position Indication (TS 3.1.7)

Not Used

2.8 Control Bank Insertion Limits (TS 3.1.6)

Figure A3 (page 14B-A9) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO = 230 steps 1(§)

withdrawn.

2.9 Axial Flux Difference (AFD) (TS 3.2.3)

Figure A4 (page 14B-A10) or, within a + /- 2% or + /- 3% target band about the target flux difference during Base Load operation.

PT= Reactor power at which predicted Fo would exceed its limit (consistent with SR 3.2.1.2).

14B-A5 Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

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:

[FaJM(Z):S [F~t x[K(Z)] for P > 0.5

[F 0 JM(Z):S [:~L x[K(Z)] for P ~ 0.5

where:

p = Thermal Power Rated Thermal Power

[F 0 JM= The Measured Value,

[Fo]L = 2.40

K(z) = 1.0 For O'.:s. z.:s. 12' where z is core height in ft

N OTES------------------------------------------------------

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 [F6Z)]/[Fo(Z)]Rs Meas.

5. [Fo(Z)]RB Meas. =[Fxy(Z)]Map Meas. x Fz(Z) x 1.09

6. [F6 (Z)] = [F6] x K(Z).

SR 3.2.1.1 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).:S. F6(Z)

Where F~ (Z) is the measured Fo(Z) increased by the allowance for manufacturing tolerances and measurement uncertainty and F6 (Z) is the Fa 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:

(( [Fo] FtZ) ]-1]x xK(Z)/P 100 for P ~ 0.5

(( [Fa] :~cz) ]-1]x xK(Z)/0.5 100 for P < 0.5

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.

148-A6 Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

SR 3.2.1.2 MIDS MIDS Operation is permitted at power above PT where PT equals the ratio of [Fa]L divided by [Fa]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

[Fa]L/P times K(Z) is not exceeded.

b. MIDS shall be operable when the thermal power exceeds PT with:

1. At least two thimbles available for which Ri and Oi 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b) Maintain the AFD (Delta-I) within a +/- 2% or +/- 3% target band for at least 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months per 24-hour period.

c) After 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 specified 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months per 24-hour period, c) Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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).

14B-A6a Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

b. Base Load operation is permitted provided:

1. THERMAL POWER is maintained between PT and PsL or between PT 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 PT are defined as:

L PsL = [Fo] xK(Z)

FM(Z)xW(Z)BLx1.09 PT= [Fo]L/[Fo]P

where: F~ (z) is the measured Fo(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. [Fo]L is the Fa limit. K(Z) is given in the COLR Section 2.10.

W(z)sL is the cycle 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 PT, then the preconditions for Base Load operation in a. above shall be satisfied before re-entering Base Load operation.

Radial Burndown

Radial Burndown operation is permitted at powers above PT if the following Radial Burndown condition is satisfied:

a. Radial Burndown operation is restricted to use at powers between PT and PRs or PT 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 [F6Z)]/[Fo(Z)]Rs Meas.

where: [Fo(Z)]RB Meas. =[Fxy(Z)]Map Meas. x Fz(Z) x 1.09 and

[F6 Z] is equal to [F6] 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 PT and PRs, or PT and 1.00 (whichever is most limiting) provided that the AFD (Delta-I) is within +/- 5% of the target axial offset.

14B-A6b Revised 05/10/2024 Turkey Point Unit 4 Cycle 34 Core Operating Limits Report

2.11 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (TS 3.2.2)

FNAH ~ FAHRTP [1.0 + PFAH(1-P)]

Where:

FAHRTP = 1.650 PFAH = 0.3

FAHRTP = FAH limit at RTP

PFAH = Power Factor Multiplier for FAH 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 ~ 585.0 °F Pressurizer Pressure ~ 2204 psig RCS total flow rate ~ 270,000 gpm 2.13 Shutdown Bank Insertion Limits (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 :5 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 PT 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 PT) 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.

14B-A6c Revised 05/10/2024

L-2024-073, Cycle 34 Core Operating Limits Report

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