NL-25-0404, Cycle 34 Core Operating Limits Report

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Cycle 34 Core Operating Limits Report
ML25296A467
Person / Time
Site: Farley 
Issue date: 10/23/2025
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
NL-25-0404
Download: ML25296A467 (1)
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Text

3535 Colonnade Parkway Birmingham, AL 35243 (205) 992-5000 Regulatory Affairs NL-25-0404 October 2, 2025 Docket No.:

50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Cycle 34 Core Operating Limits Report Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLR) for the Joseph M.

Farley Nuclear Plant (FNP) - Unit 1 Cycle 34 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.

Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director JMC/was/cbg

Enclosure:

Core Operating Limits Report for FNP Unit 1 Cycle 34 Version 1 cc: Regional Administrator, Region ll NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054 Digitally signed by JAMIEMCO Date: 2025.10.23 11:28:16 -05'00'

Joseph M. Farley Nuclear Plant - Unit 1 Cycle 34 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 34 Version 1

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 34 Version 1 JULY 2025

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 1 of 20 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 34 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical Requirement affected by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 (with keff t1)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with keff < 1), 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor - ()

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor -



3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature 'T (OT'T) and Overpower 'T (OP'T) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 2 of 20 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC-approved methodologies as specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES 1 and 2 (with keff t1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent 'k/k.

2.2 SHUTDOWN MARGIN - MODES 2 (with keff < 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keff < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent 'k/k.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent 'k/k.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 3 of 20 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL/ARO-MTC shall be less than or equal to +0.7 x 10-4 'k/k/qF for power levels up to 70 percent RTP with a linear ramp to 0 'k/k/qF at 100 percent RTP.

The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 10-4 'k/k/qF.

2.3.2 The MTC Surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-3.65 x 10-4 'k/k/qF.

The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5 and the following algorithm:

Revised Predicted MTC = Predicted MTC* + AFD Correction** + Predictive Correction***

where,
  • Predicted MTC is calculated from Figure 5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcm/°F or (¨AFD

  • AFD Sensitivity)}

ZKHUH¨AFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm, AFD Sensitivity = 0.07 pcm/°)¨AFD

      • Predictive Correction is -3 pcm/°F.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 10-4'k/k/qF.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 4 of 20 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.

2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.6 Heat Flux Hot Channel Factor - () (Specification 3.2.1) 2.6.1

()

()

for P > 0.5

()

. ()

for P d 0.5 where:

() =

()

0F§

() is the measured value of ()

=

2.6.2

= 2.50 2.6.3

() is provided in Figure 2.

2.6.4

()

()

for P > 0.5

()

. ()

for P d 0.5 where:

() = [()]

[()]

()

§ for P > 0.5

() = [()]

[()]

()

§ for P d 0.5 and, [()]

is the measured planar radial peaking factor.

() evaluations are not applicable for axial core regions, measured in percent of core height:

a. Lower core region, from 0 to 8% inclusive,
b. Upper core region, from 92 to 100% inclusive,

§. The uncertainty factor (

) used during the Fq surveillance must be consistent with Technical Specification B 3.2.1-3.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 5 of 20

c. Grid plane regions, +/- 2% inclusive, and
d. Core plane regions, within +/- 2% of the bank demand position of the control banks.

2.6.5

[()] values are provided in Table 4-1 for ROS1 and Table 4-2 for ROS2.

2.6.6 The () factors adjust the surveillance to the reference conditions assumed in generating the [()] factors. () may be assumed to equal 1.0 or may be determined for specific surveillance conditions using the approved methods listed in Technical Specification 5.6.5.

2.6.7 The penalty factors account for the potential decrease in transient margin between surveillances. The factors are provided in Table 1-1 for ROS1 and Table 1-2 for ROS2.

2.6.8 Table 5 provides the required limits on THERMAL POWER and the required AFD reductions in the event that additional margin is required.

2.6.9 Either ROS1 or ROS2 may be implemented at any time during the Cycle.

2.6.10 If ROS1 is implemented and entering LCO 3.2.1 Condition B for

() not within limits, take Action B.1.1 by implementing ROS2.

2.6.11 If ROS2 is implemented and entering LCO 3.2.1 Condition B for

() not within limits, take Action B.2.1 by using Table 5 to determine required THERMAL POWER and AFD limits based on Required

() margin improvement available in ROS2.

2.7 Nuclear Enthalpy Rise Hot Channel Factor -

(Specification 3.2.2) 2.7.1

1 + (1 )

where:

=

2.7.2

= 1.70 2.7.3

= 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits for each RAOC Operating Space (ROS1 and ROS2), and corresponding Required Action (RA1 and RA2) are provided in Figure 3.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 6 of 20 2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm.1 2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.

2.11 Reactor Trip System Instrumentation Overtemperature T (OTT) and Overpower T (OPT)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature T (OTT) and Overpower T (OPT) setpoint parameter values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

2.12 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

D

Pressurizer pressure t 2209 psig; E

RCS average temperature d 580.qF; and F

The minimum RCS total flow rate shall be t 273,900 GPM when using the precision

heat balance method and t 274,800 GPM when using the elbow tap method.

1 This concentration bounds the condition of keff d 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 7 of 20 Table 1-1 Margin Decrease Factors for ROS1 Cycle Burnup (MWD/MTU)

Cycle Burnup (MWD/MTU)

Cycle Burnup (MWD/MTU)



1.0313 7216 1.0222 14282 1.0049 358 1.0306 7424 1.0229 14490 1.0036 566 1.0287 7632 1.0184 14698 1.0025 773 1.0259 7840 1.0135 14906 1.0016 981 1.0220 8047 1.0094 15113 1.0006 1189 1.0177 8255 1.0061 15321 1.0002 1397 1.0148 8463 1.0034 15529 1.0000 1605 1.0126 8671 1.0014 15737 1.0000 1813 1.0121 8879 1.0009 15945 1.0000 2020 1.0148 9086 1.0085 16152 1.0000 2228 1.0151 9294 1.0100 16360 1.0000 2436 1.0147 9502 1.0110 16568 1.0000 2644 1.0157 9710 1.0124 16776 1.0000 2852 1.0148 9918 1.0136 16984 1.0000 3060 1.0132 10126 1.0145 17192 1.0000 3267 1.0107 10333 1.0153 17399 1.0000 3475 1.0077 10541 1.0161 17607 1.0000 3683 1.0023 10749 1.0170 17815 1.0000 3891 1.0004 10957 1.0178 18023 1.0000 4099 1.0000 11165 1.0190 18231 1.0005 4306 1.0000 11373 1.0241 18439 1.0015 4514 1.0049 11580 1.0246 18646 1.0019 4722 1.0073 11788 1.0248 18854 1.0021 4930 1.0086 11996 1.0247 19062 1.0022 5138 1.0089 12204 1.0241 19270 1.0020 5346 1.0087 12412 1.0231 19478 1.0016 5553 1.0043 12619 1.0218 19686 1.0011 5761 1.0030 12827 1.0204 19893 1.0004 5969 1.0042 13035 1.0143 20101 1.0000 6177 1.0081 13243 1.0126 20309 1.0000 6385 1.0116 13451 1.0113 6593 1.0147 13659 1.0096 6800 1.0175 13866 1.0080 7008 1.0203 14074 1.0063 Notes:

1. The Burnup Dependent Transient Margin Decrease Factor, to be applied to () in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which () is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting from the burnup at which the () was determined.
2. Values may be interpolated to the surveillance cycle burnup.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 8 of 20 Table 1-2 Margin Decrease Factors for ROS2 Cycle Burnup (MWD/MTU)

Cycle Burnup (MWD/MTU)

Cycle Burnup (MWD/MTU)



1.0092 7216 1.0000 14282 1.0032 358 1.0115 7424 1.0000 14490 1.0029 566 1.0126 7632 1.0000 14698 1.0025 773 1.0128 7840 1.0000 14906 1.0021 981 1.0120 8047 1.0000 15113 1.0025 1189 1.0111 8255 1.0000 15321 1.0021 1397 1.0105 8463 1.0023 15529 1.0017 1605 1.0104 8671 1.0055 15737 1.0013 1813 1.0112 8879 1.0087 15945 1.0009 2020 1.0127 9086 1.0118 16152 1.0007 2228 1.0149 9294 1.0148 16360 1.0004 2436 1.0171 9502 1.0182 16568 1.0002 2644 1.0191 9710 1.0183 16776 1.0001 2852 1.0214 9918 1.0182 16984 1.0000 3060 1.0206 10126 1.0212 17192 1.0000 3267 1.0181 10333 1.0240 17399 1.0000 3475 1.0151 10541 1.0229 17607 1.0000 3683 1.0120 10749 1.0215 17815 1.0000 3891 1.0102 10957 1.0195 18023 1.0000 4099 1.0088 11165 1.0149 18231 1.0000 4306 1.0069 11373 1.0133 18439 1.0000 4514 1.0033 11580 1.0119 18646 1.0000 4722 1.0014 11788 1.0107 18854 1.0000 4930 1.0002 11996 1.0096 19062 1.0000 5138 1.0000 12204 1.0088 19270 1.0000 5346 1.0000 12412 1.0083 19478 1.0000 5553 1.0000 12619 1.0080 19686 1.0000 5761 1.0000 12827 1.0073 19893 1.0000 5969 1.0000 13035 1.0068 20101 1.0000 6177 1.0000 13243 1.0062 20309 1.0000 6385 1.0000 13451 1.0051 6593 1.0001 13659 1.0044 6800 1.0018 13866 1.0040 7008 1.0000 14074 1.0036 Notes:

1. The Burnup Dependent Transient Margin Decrease Factor, to be applied to () in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which () is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting from the burnup at which the () was determined.
2. Values may be interpolated to the surveillance cycle burnup.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 9 of 20 Table 2 Reactor Trip System Instrumentation - Overtemperature T (OT'T)

Setpoint Parameter Values Tc d 577.2qF Pc = 2235 psig K1 = 1.17 K2 = 0.017/qF K3 = 0.000825/psi W1 t 30 sec W2 d 4 sec W4 = 0 sec W5 d 6 sec W6 d 6 sec f1('I) =

-2.48 {23 + (qt - qb)}

when (qt - qb) d -23% RTP 0% of RTP when -23% RTP < (qt -qb) d 15% RTP 2.05 {(qt - qb) - 15}

when (qt - qb) > 15% RTP

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 10 of 20 Table 3 Reactor Trip System Instrumentation - Overpower T (OP'T)

Setpoint Parameter Values Tcc d 577.2qF K4 = 1.10 K5 = 0.02/qF for increasing Tavg K6 = 0.00109/qF when T > Tcc K5 = 0/qF for decreasing Tavg K6 = 0/qF when T d Tcc W3 t 10 sec W4 = 0 sec W5 d 6 sec W6 d 6 sec f2('I) = 0% RTP for all 'I

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 11 of 20 Table 4-1

[()] Factors for ROS1 Axial Point Elevation (feet) 150 MWD/MTU 1000 MWD/MTU 2000 MWD/MTU 3000 MWD/MTU 4000 MWD/MTU 5000 MWD/MTU 6000 MWD/MTU 1

12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

11.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

11.00 1.0812 1.0211 0.9956 0.9693 0.9722 0.9779 0.9860 7

10.80 1.0802 1.0270 1.0082 0.9880 0.9952 1.0024 1.0144 8

10.60 1.1357 1.0920 1.0799 1.0624 1.0722 1.0803 1.0936 9

10.40 1.2173 1.1766 1.1706 1.1552 1.1666 1.1721 1.1884 10 10.20 1.2457 1.2098 1.2100 1.1971 1.2099 1.2128 1.2312 11 10.00 1.2084 1.1867 1.1859 1.1976 1.1907 1.1920 1.2118 12 9.80 1.2189 1.2122 1.2062 1.2289 1.2132 1.2177 1.2323 13 9.60 1.2790 1.2799 1.2781 1.3013 1.2874 1.2906 1.2972 14 9.40 1.2771 1.2909 1.2865 1.3149 1.2972 1.3039 1.3105 15 9.20 1.2290 1.2454 1.2507 1.2717 1.2636 1.2660 1.2718 16 9.00 1.2108 1.2316 1.2394 1.2605 1.2521 1.2502 1.2569 17 8.80 1.2706 1.2939 1.3152 1.3224 1.3238 1.3042 1.3131 18 8.60 1.3296 1.3548 1.3795 1.3805 1.3901 1.3489 1.3658 19 8.40 1.3225 1.3518 1.3780 1.3809 1.3886 1.3454 1.3619 20 8.20 1.2858 1.3169 1.3444 1.3487 1.3566 1.3169 1.3288 21 8.00 1.3455 1.3777 1.4062 1.4101 1.4160 1.3756 1.3815 22 7.80 1.3919 1.4255 1.4546 1.4582 1.4624 1.4212 1.4222 23 7.60 1.3640 1.3985 1.4279 1.4326 1.4362 1.3972 1.3955 24 7.40 1.3076 1.3426 1.3718 1.3778 1.3813 1.3455 1.3426 25 7.20 1.3223 1.3599 1.3893 1.3954 1.3976 1.3609 1.3567 26 7.00 1.3791 1.4192 1.4486 1.4543 1.4543 1.4145 1.4098 27 6.80 1.3906 1.4298 1.4587 1.4645 1.4633 1.4250 1.4190 28 6.60 1.3313 1.3683 1.3965 1.4036 1.4028 1.3711 1.3642 29 6.40 1.3077 1.3425 1.3698 1.3776 1.3764 1.3499 1.3412 30 6.20 1.3587 1.3919 1.4179 1.4249 1.4216 1.3976 1.3851 31 6.00 1.3507 1.3814 1.4060 1.4134 1.4095 1.3906 1.3762 32 5.80 1.2846 1.3121 1.3355 1.3441 1.3410 1.3285 1.3142 33 5.60 1.2363 1.2610 1.2849 1.2977 1.2933 1.2805 1.2689 34 5.40 1.2653 1.2936 1.3352 1.3488 1.3466 1.3264 1.3030 35 5.20 1.2938 1.3335 1.3758 1.3897 1.3866 1.3652 1.3377 36 5.00 1.2918 1.3277 1.3711 1.3854 1.3830 1.3617 1.3375 37 4.80 1.2869 1.3203 1.3638 1.3785 1.3767 1.3561 1.3351 38 4.60 1.2911 1.3217 1.3652 1.3801 1.3788 1.3588 1.3410 39 4.40 1.3020 1.3294 1.3726 1.3875 1.3866 1.3674 1.3529 40 4.20 1.2844 1.3082 1.3500 1.3650 1.3652 1.3477 1.3377 41 4.00 1.2278 1.2471 1.2869 1.3021 1.3037 1.2904 1.2853 42 3.80 1.2260 1.2439 1.2796 1.2939 1.2981 1.2872 1.2848 43 3.60 1.2742 1.2956 1.3249 1.3356 1.3433 1.3319 1.3343 44 3.40 1.2829 1.3072 1.3297 1.3359 1.3479 1.3384 1.3467 45 3.20 1.2633 1.2913 1.3066 1.3085 1.3231 1.3177 1.3324 46 3.00 1.2593 1.2814 1.2976 1.3027 1.3157 1.3153 1.3215 47 2.80 1.2760 1.2916 1.3109 1.3130 1.3266 1.3284 1.3266 48 2.60 1.2919 1.3106 1.3293 1.3188 1.3387 1.3368 1.3411 49 2.40 1.2673 1.2881 1.3049 1.2833 1.3090 1.3104 1.3175 50 2.20 1.2223 1.2445 1.2585 1.2311 1.2570 1.2630 1.2713 51 2.00 1.2563 1.2754 1.2856 1.2512 1.2751 1.2839 1.2929 52 1.80 1.3104 1.3247 1.3297 1.2866 1.3078 1.3187 1.3272 53 1.60 1.3171 1.3247 1.3232 1.2731 1.2903 1.3028 1.3110 54 1.40 1.2854 1.2860 1.2780 1.2228 1.2358 1.2492 1.2573 55 1.20 1.2482 1.2409 1.2255 1.1652 1.1734 1.1864 1.1932 56 1.00 1.2616 1.2393 1.2119 1.1381 1.1381 1.1471 1.1499 57 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Notes (per Technical Specification Bases page B 3.2.1-13):

1. Top and bottom 5 Axial Points (8%) are excluded.
2. Axial points within +/- 2% of the active core height of a grid location or a bank demand position are excluded.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 12 of 20 Table 4-1 (Continued)

[()] Factors for ROS1 Axial Point Elevation (feet) 8000 MWD/MTU 10000 MWD/MTU 12000 MWD/MTU 14000 MWD/MTU 16000 MWD/MTU 18000 MWD/MTU 20000 MWD/MTU 1

12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

11.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

11.00 1.0450 1.0879 1.1299 1.1598 1.2082 1.2196 1.2307 7

10.80 1.0732 1.1155 1.1551 1.1830 1.2268 1.2353 1.2364 8

10.60 1.1523 1.1920 1.2272 1.2472 1.2845 1.2896 1.2795 9

10.40 1.2429 1.2783 1.3076 1.3206 1.3450 1.3474 1.3328 10 10.20 1.2790 1.3089 1.3320 1.3391 1.3479 1.3500 1.3370 11 10.00 1.2528 1.2779 1.2961 1.2998 1.3065 1.3000 1.2928 12 9.80 1.2656 1.2846 1.2986 1.3020 1.3019 1.2919 1.2800 13 9.60 1.3212 1.3304 1.3501 1.3464 1.3354 1.3195 1.2995 14 9.40 1.3286 1.3320 1.3417 1.3413 1.3266 1.3026 1.2922 15 9.20 1.2833 1.2868 1.3009 1.2901 1.2785 1.2594 1.2544 16 9.00 1.2670 1.2672 1.2776 1.2703 1.2569 1.2408 1.2371 17 8.80 1.3192 1.3246 1.3153 1.3069 1.2960 1.2814 1.2748 18 8.60 1.3700 1.3672 1.3448 1.3332 1.3210 1.3118 1.3111 19 8.40 1.3626 1.3543 1.3321 1.3190 1.3031 1.2992 1.3023 20 8.20 1.3278 1.3141 1.2932 1.2852 1.2736 1.2764 1.2809 21 8.00 1.3746 1.3550 1.3347 1.3233 1.3086 1.3161 1.3201 22 7.80 1.4097 1.3834 1.3641 1.3503 1.3352 1.3462 1.3508 23 7.60 1.3809 1.3522 1.3363 1.3240 1.3125 1.3269 1.3347 24 7.40 1.3273 1.2983 1.2864 1.2772 1.2703 1.2879 1.2999 25 7.20 1.3368 1.3035 1.2914 1.2836 1.2774 1.2962 1.3115 26 7.00 1.3820 1.3437 1.3273 1.3202 1.3121 1.3310 1.3492 27 6.80 1.3859 1.3460 1.3266 1.3220 1.3163 1.3331 1.3552 28 6.60 1.3307 1.2937 1.2737 1.2747 1.2740 1.2892 1.3168 29 6.40 1.3054 1.2693 1.2507 1.2520 1.2548 1.2665 1.2987 30 6.20 1.3424 1.3028 1.2824 1.2808 1.2842 1.2913 1.3249 31 6.00 1.3310 1.2916 1.2720 1.2693 1.2748 1.2817 1.3141 32 5.80 1.2710 1.2355 1.2192 1.2171 1.2260 1.2368 1.2657 33 5.60 1.2305 1.1963 1.1783 1.1790 1.1892 1.2070 1.2298 34 5.40 1.2595 1.2262 1.2170 1.2169 1.2277 1.2383 1.2594 35 5.20 1.2911 1.2612 1.2494 1.2439 1.2554 1.2628 1.2815 36 5.00 1.2896 1.2614 1.2497 1.2404 1.2535 1.2600 1.2752 37 4.80 1.2872 1.2603 1.2483 1.2367 1.2499 1.2574 1.2662 38 4.60 1.2946 1.2686 1.2559 1.2417 1.2522 1.2598 1.2652 39 4.40 1.3073 1.2822 1.2685 1.2519 1.2590 1.2660 1.2673 40 4.20 1.2953 1.2728 1.2592 1.2416 1.2459 1.2528 1.2505 41 4.00 1.2501 1.2319 1.2206 1.2063 1.2065 1.2142 1.2097 42 3.80 1.2540 1.2370 1.2248 1.2144 1.2058 1.2129 1.2033 43 3.60 1.3039 1.2830 1.2723 1.2592 1.2456 1.2448 1.2326 44 3.40 1.3209 1.2989 1.2931 1.2737 1.2629 1.2520 1.2419 45 3.20 1.3127 1.2923 1.2935 1.2763 1.2620 1.2399 1.2344 46 3.00 1.3149 1.3024 1.2972 1.2865 1.2711 1.2507 1.2383 47 2.80 1.3398 1.3277 1.3156 1.3194 1.3053 1.2815 1.2702 48 2.60 1.3650 1.3516 1.3433 1.3543 1.3424 1.3112 1.3073 49 2.40 1.3499 1.3406 1.3388 1.3554 1.3482 1.3185 1.3159 50 2.20 1.3126 1.3093 1.3188 1.3426 1.3416 1.3164 1.3189 51 2.00 1.3420 1.3418 1.3532 1.3829 1.3861 1.3623 1.3666 52 1.80 1.3829 1.3849 1.4015 1.4375 1.4452 1.4228 1.4293 53 1.60 1.3723 1.3788 1.4025 1.4465 1.4616 1.4445 1.4561 54 1.40 1.3224 1.3342 1.3657 1.4180 1.4418 1.4324 1.4508 55 1.20 1.2593 1.2749 1.3126 1.3720 1.4043 1.4031 1.4288 56 1.00 1.2119 1.2275 1.2687 1.3337 1.3738 1.3814 1.4158 57 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Notes (per Technical Specification Bases page B 3.2.1-13):

1. Top and bottom 5 Axial Points (8%) are excluded.
2. Axial points within +/- 2% of the active core height of a grid location or a bank demand position are excluded.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 13 of 20 Table 4-2

[()] Factors for ROS2 Axial Point Elevation (feet) 150 MWD/MTU 1000 MWD/MTU 2000 MWD/MTU 3000 MWD/MTU 4000 MWD/MTU 5000 MWD/MTU 6000 MWD/MTU 1

12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

11.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

11.00 1.0355 0.9757 0.9430 0.9120 0.9090 0.9167 0.9280 7

10.80 1.0325 0.9789 0.9542 0.9291 0.9322 0.9411 0.9559 8

10.60 1.0844 1.0398 1.0215 0.9989 1.0065 1.0177 1.0321 9

10.40 1.1576 1.1201 1.1048 1.0886 1.0974 1.1155 1.1235 10 10.20 1.1842 1.1531 1.1444 1.1407 1.1410 1.1630 1.1661 11 10.00 1.1510 1.1347 1.1276 1.1439 1.1296 1.1489 1.1503 12 9.80 1.1690 1.1611 1.1569 1.1761 1.1600 1.1774 1.1724 13 9.60 1.2360 1.2280 1.2247 1.2479 1.2336 1.2476 1.2417 14 9.40 1.2466 1.2408 1.2473 1.2637 1.2547 1.2605 1.2528 15 9.20 1.2030 1.1994 1.2069 1.2250 1.2168 1.2239 1.2227 16 9.00 1.1891 1.1884 1.1935 1.2173 1.2067 1.2090 1.2112 17 8.80 1.2528 1.2534 1.2576 1.2791 1.2691 1.2716 1.2701 18 8.60 1.3163 1.3182 1.3196 1.3269 1.3289 1.3336 1.3271 19 8.40 1.3114 1.3161 1.3183 1.3201 1.3287 1.3338 1.3241 20 8.20 1.2764 1.2838 1.2901 1.2943 1.3019 1.3054 1.2936 21 8.00 1.3357 1.3449 1.3548 1.3588 1.3646 1.3632 1.3468 22 7.80 1.3825 1.3934 1.4063 1.4100 1.4142 1.4090 1.3885 23 7.60 1.3561 1.3690 1.3846 1.3893 1.3930 1.3866 1.3647 24 7.40 1.3018 1.3163 1.3338 1.3398 1.3434 1.3371 1.3152 25 7.20 1.3194 1.3357 1.3537 1.3598 1.3622 1.3554 1.3312 26 7.00 1.3786 1.3967 1.4140 1.4196 1.4200 1.4126 1.3860 27 6.80 1.3903 1.4098 1.4259 1.4317 1.4305 1.4246 1.3979 28 6.60 1.3310 1.3519 1.3674 1.3744 1.3763 1.3707 1.3468 29 6.40 1.3074 1.3294 1.3473 1.3549 1.3567 1.3495 1.3272 30 6.20 1.3584 1.3814 1.4010 1.4081 1.4080 1.3971 1.3740 31 6.00 1.3505 1.3743 1.3959 1.4034 1.4028 1.3902 1.3685 32 5.80 1.2844 1.3085 1.3319 1.3404 1.3406 1.3281 1.3102 33 5.60 1.2362 1.2604 1.2855 1.2956 1.2955 1.2834 1.2683 34 5.40 1.2645 1.2914 1.3209 1.3343 1.3307 1.3213 1.3028 35 5.20 1.2834 1.3205 1.3502 1.3673 1.3607 1.3489 1.3321 36 5.00 1.2715 1.3089 1.3426 1.3597 1.3540 1.3392 1.3223 37 4.80 1.2576 1.2981 1.3308 1.3482 1.3433 1.3304 1.3156 38 4.60 1.2582 1.2979 1.3301 1.3474 1.3432 1.3314 1.3185 39 4.40 1.2646 1.3031 1.3342 1.3512 1.3477 1.3378 1.3273 40 4.20 1.2438 1.2802 1.3100 1.3263 1.3242 1.3183 1.3098 41 4.00 1.1855 1.2196 1.2499 1.2626 1.2623 1.2622 1.2563 42 3.80 1.1819 1.2164 1.2453 1.2516 1.2546 1.2571 1.2529 43 3.60 1.2297 1.2644 1.2893 1.2920 1.2969 1.2982 1.2951 44 3.40 1.2399 1.2724 1.2930 1.2955 1.3003 1.3018 1.2999 45 3.20 1.2231 1.2536 1.2694 1.2692 1.2745 1.2779 1.2795 46 3.00 1.2210 1.2394 1.2504 1.2651 1.2697 1.2732 1.2642 47 2.80 1.2368 1.2426 1.2602 1.2772 1.2811 1.2812 1.2718 48 2.60 1.2562 1.2542 1.2740 1.2888 1.2923 1.2873 1.2830 49 2.40 1.2358 1.2286 1.2467 1.2604 1.2637 1.2544 1.2556 50 2.20 1.1958 1.1827 1.1989 1.2106 1.2136 1.2024 1.2074 51 2.00 1.2293 1.2079 1.2211 1.2300 1.2312 1.2187 1.2238 52 1.80 1.2817 1.2505 1.2595 1.2645 1.2629 1.2482 1.2541 53 1.60 1.2878 1.2469 1.2503 1.2507 1.2463 1.2301 1.2371 54 1.40 1.2564 1.2074 1.2049 1.2008 1.1939 1.1770 1.1846 55 1.20 1.2197 1.1624 1.1533 1.1440 1.1339 1.1156 1.1227 56 1.00 1.2325 1.1586 1.1365 1.1173 1.1000 1.0768 1.0805 57 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Notes (per Technical Specification Bases page B 3.2.1-13):

1. Top and bottom 5 Axial Points (8%) are excluded.
2. Axial points within +/- 2% of the active core height of a grid location or a bank demand position are excluded.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 14 of 20 Table 4-2 (Continued)

[()] Factors for ROS2 Axial Point Elevation (feet) 8000 MWD/MTU 10000 MWD/MTU 12000 MWD/MTU 14000 MWD/MTU 16000 MWD/MTU 18000 MWD/MTU 20000 MWD/MTU 1

12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2

11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3

11.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4

11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5

11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6

11.00 0.9932 1.0364 1.0788 1.1042 1.1421 1.1785 1.1802 7

10.80 1.0206 1.0630 1.1029 1.1251 1.1584 1.1915 1.1884 8

10.60 1.0967 1.1363 1.1718 1.1884 1.2145 1.2437 1.2335 9

10.40 1.1838 1.2192 1.2488 1.2588 1.2762 1.3017 1.2837 10 10.20 1.2194 1.2491 1.2724 1.2767 1.2865 1.3093 1.2867 11 10.00 1.1957 1.2204 1.2386 1.2420 1.2446 1.2665 1.2474 12 9.80 1.2095 1.2350 1.2394 1.2443 1.2407 1.2555 1.2393 13 9.60 1.2633 1.2933 1.2878 1.2841 1.2721 1.2776 1.2646 14 9.40 1.2733 1.2919 1.2822 1.2870 1.2692 1.2631 1.2622 15 9.20 1.2328 1.2557 1.2456 1.2363 1.2247 1.2288 1.2224 16 9.00 1.2202 1.2367 1.2258 1.2130 1.2091 1.2107 1.2098 17 8.80 1.2754 1.2828 1.2661 1.2644 1.2488 1.2446 1.2449 18 8.60 1.3297 1.3250 1.3001 1.3039 1.2870 1.2659 1.2678 19 8.40 1.3240 1.3144 1.2894 1.2938 1.2775 1.2507 1.2546 20 8.20 1.2921 1.2790 1.2535 1.2626 1.2482 1.2276 1.2360 21 8.00 1.3399 1.3213 1.2921 1.2993 1.2830 1.2635 1.2746 22 7.80 1.3766 1.3553 1.3198 1.3269 1.3093 1.2914 1.3052 23 7.60 1.3510 1.3295 1.2932 1.3021 1.2866 1.2729 1.2908 24 7.40 1.3011 1.2805 1.2460 1.2572 1.2450 1.2379 1.2585 25 7.20 1.3132 1.2889 1.2535 1.2648 1.2531 1.2501 1.2714 26 7.00 1.3608 1.3299 1.2928 1.3023 1.2896 1.2881 1.3100 27 6.80 1.3677 1.3324 1.2980 1.3057 1.2952 1.2934 1.3181 28 6.60 1.3163 1.2804 1.2531 1.2606 1.2549 1.2569 1.2831 29 6.40 1.2946 1.2570 1.2340 1.2400 1.2375 1.2425 1.2683 30 6.20 1.3348 1.2938 1.2687 1.2704 1.2683 1.2736 1.2970 31 6.00 1.3269 1.2862 1.2620 1.2610 1.2609 1.2681 1.2898 32 5.80 1.2704 1.2338 1.2131 1.2112 1.2147 1.2263 1.2459 33 5.60 1.2295 1.1955 1.1775 1.1726 1.1813 1.1998 1.2149 34 5.40 1.2597 1.2201 1.2020 1.2078 1.2136 1.2283 1.2444 35 5.20 1.2906 1.2514 1.2290 1.2333 1.2359 1.2509 1.2642 36 5.00 1.2845 1.2481 1.2255 1.2288 1.2304 1.2451 1.2572 37 4.80 1.2766 1.2445 1.2225 1.2232 1.2242 1.2368 1.2493 38 4.60 1.2782 1.2483 1.2264 1.2242 1.2253 1.2351 1.2472 39 4.40 1.2859 1.2584 1.2362 1.2304 1.2303 1.2366 1.2472 40 4.20 1.2719 1.2462 1.2251 1.2167 1.2159 1.2195 1.2291 41 4.00 1.2252 1.2034 1.1854 1.1762 1.1761 1.1781 1.1875 42 3.80 1.2258 1.2055 1.1893 1.1756 1.1741 1.1723 1.1803 43 3.60 1.2689 1.2476 1.2348 1.2162 1.2083 1.2025 1.2043 44 3.40 1.2809 1.2592 1.2519 1.2327 1.2206 1.2131 1.2033 45 3.20 1.2709 1.2499 1.2482 1.2300 1.2161 1.2084 1.1987 46 3.00 1.2696 1.2543 1.2542 1.2342 1.2219 1.2090 1.2037 47 2.80 1.2858 1.2738 1.2795 1.2615 1.2506 1.2359 1.2318 48 2.60 1.3056 1.2912 1.3059 1.2925 1.2825 1.2696 1.2653 49 2.40 1.2868 1.2793 1.2978 1.2911 1.2846 1.2755 1.2714 50 2.20 1.2473 1.2491 1.2753 1.2768 1.2753 1.2714 1.2722 51 2.00 1.2713 1.2794 1.3054 1.3130 1.3148 1.3139 1.3162 52 1.80 1.3062 1.3197 1.3490 1.3628 1.3680 1.3704 1.3746 53 1.60 1.2929 1.3129 1.3474 1.3697 1.3811 1.3898 1.3988 54 1.40 1.2431 1.2695 1.3099 1.3413 1.3605 1.3768 1.3923 55 1.20 1.1813 1.2121 1.2572 1.2966 1.3235 1.3475 1.3699 56 1.00 1.1349 1.1662 1.2137 1.2593 1.2935 1.3257 1.3565 57 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Notes (per Technical Specification Bases page B 3.2.1-13):

1. Top and bottom 5 Axial Points (8%) are excluded.
2. Axial points within +/- 2% of the active core height of a grid location or a bank demand position are excluded.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 15 of 20 Table 5 Required THERMAL POWER Limits and AFD Reductions RAOC Operating Space Required FQW(z) Margin Improvement (%)

Required THERMAL POWER Limit (%RTP)

Required AFD Reduction ROS1

> 0

< 50 N/A ROS2





See Figure 3

> DQG3.9



> 3.9

< 50

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 16 of 20 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive Fully Withdrawn shall be the condition where control rods are at a position within the interval t 225 and d 231 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 128 steps.

0 25 50 75 100 125 150 175 200 225 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Rod Bank Position (Steps Withdrawn)

Fraction of RATED THERMAL POWER Bank D

(.070, 0)

(1, 187)

Bank C (0, 114)

(.552, 225)

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 17 of 20 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 0

0.2 0.4 0.6 0.8 1

1.2 0

2 4

6 8

10 12 K(Z) - Normalized Peaking Factor Core Height (feet)

Core Height (ft.)

0.000 6.000 12.000 K(Z) 1.000 1.000 1.000 FQ = 2.50

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 18 of 20 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for ROS1, ROS2, RA1 and RA2 0

10 20 30 40 50 60 70 80 90 100 110

-50

-40

-30

-20

-10 0

10 20 30 40 50 Power (% of RATED THERMAL POWER)

Axial Flux Difference (Delta I) %

ROS1 ROS2 RA1 RA2 ACCEPTABLE OPERATION UNACCEPTABLE OPERATION UNACCEPTABLE OPERATION

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 19 of 20 Figure 4 Reactor Core Safety Limits 560 580 600 620 640 660 680 0

0.2 0.4 0.6 0.8 1

1.2 Tavg (degree F)

Power (Fraction of RATED THERMAL POWER) 2425 psig 2235 psig 1985 psig 1831 psig UNACCEPTABLE OPERATION ACCEPTABLE OPERATION

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 34 JULY 2025 Page 20 of 20 Figure 5 Predicted HFP 300 ppm MTC versus Cycle Burnup Cycle Burnup Moderator Temperature (MWD/MTU)

Coefficient (pcm/°F) 15000

-24.54 16000

-24.81 17000

-25.04 18000

-25.29 19000

-25.48

-26.0

-25.5

-25.0

-24.5

-24.0 15000 16000 17000 18000 19000 Moderator Temperature Coefficient (pcm/°F)

Cycle Burnup (MWD/MTU)

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