L-2023-048, Core Operating Limits Report (COLR) Cycle 40 (U2C40)

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Core Operating Limits Report (COLR) Cycle 40 (U2C40)
ML23077A001
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 03/18/2023
From: Strand D
Point Beach
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
L-2023-048, TS 5.6.4
Download: ML23077A001 (1)
v • d • e


Text

L-2023-048 TS 5.6.4 March 18, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant, Unit 2 Docket: 50-301 License: DPR-27 Core Operating Limits Report (COLR) Unit 2 Cycle 40 (U2C40)

In accordance with the requirements of Point Beach Nuclear Plant (PBNP)

Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 2, Cycle 40.

The Enclosure to this letter contains TRM 2.1 for Unit 2 issued on March 18, 2023.

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

Sincerely, Dianne Strand General Manager Regulatory Affairs Enclosure Point Beach Unit 2, Cycle 40 Core Operating Limits Report cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241

TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 REVISION 23

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Point Beach Nuclear Plant has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.4.

A cross-reference between the COLR sections and the PBNP Technical Specifications affected by this report is given below:

COLR PBNP Description Section TS 2.1 2.1.1 Reactor Core Safety Limits 2.2 3.1.1 Shutdown Margin 3.1.4 Rod Group Alignment Limits 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.8 Physics Test Exceptions 2.3 3.1.3 Moderator Temperature Coefficient 2.4 3.1.5 Shutdown Bank Insertion Limit 2.5 3.1.6 Control Bank Insertion Limits 2.6 3.2.1 Nuclear Heat Flux Hot Channel Factor (FQ(Z))

2.7 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH) 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature T Setpoint 2.10 3.3.1 Overpower T Setpoint 2.11 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 3.9.1 Refueling Boron Concentration Figure 1 2.1.1 Reactor Core Safety Limits Curve Figure 2 3.1.1 Required Shutdown Margin Figure 3 3.1.6 Control Bank Insertion Limits Figure 4 3.2.1 Hot Channel Factor Normalized Operating Envelope (K(Z))

Figure 5A 3.2.1 W(Z) function for Operating Space 6A (AFD Band of +/- 5%)

Figure 5B 3.2.1 W(Z) function for Operating Space 6B (AFD Band of +/- 3%)

Figure 5C 3.2.1 BOC Part-Power W(Z) function for Operating Space 6A (AFD Band of +/- 5%) (D-Bank 205 steps)

Figure 6A 3.2.3 Flux Difference Operating Envelope (AFD Band of +/- 5%)

Figure 6B 3.2.3 Flux Difference Operating Envelope (AFD Band of +/- 3%)

Figure 7A 3.2.1 Rj Margin Decrease Factors for Operating Space 6A (AFD Band of +/- 5%)

Figure 7B 3.2.1 Rj Margin Decrease Factors for Operating Space 6B (AFD Band of +/- 3%)

Figure 8 3.2.3 Required Thermal Power Limits Table 1 5.6.4 NRC Approved Methodologies for COLR Parameters Page 2 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 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 the NRC approved methodologies specified in Technical Specification 5.6.4.

2.1 Reactor Core Safety Limits (TS 2.1.1)

The combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 1.

Applicability: MODES 1 and 2 2.2 Shutdown Margin (TS 3.1.1 and referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.2.1 SDM shall be 2.0% k/k (see Figure 2).

Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be 1% k/k.

Applicability: MODES 4 and 5 2.3 Moderator Temperature Coefficient (TS 3.1.3) 2.3.1 The upper MTC limits shall be maintained within the limits.

2.3.2 The maximum upper MTC limits shall be:

5 pcm/°F for power levels 70% RTP 0 pcm/°F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with keff >1.0.

2.4 Shutdown Bank Insertion Limit (TS 3.1.5)

NOTE: This limit is not applicable while performing SR 3.1.4.2.

2.4.1 Each shutdown bank shall be fully withdrawn.

2.4.2 Fully withdrawn is defined as 225 steps.

Applicability: MODES 1 and 2 Page 3 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 2.5 Control Bank Insertion Limits (TS 3.1.6)

NOTE: This limit is not applicable while performing SR 3.1.4.2.

The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3 for the Operating Spaces of Figures 6A and 6B.

Applicability: MODE 1 and MODE 2 with keff 1.0 2.6 Nuclear Heat Flux Hot Channel Factor (FQ(Z)) (TS 3.2.1)

The Heat Flux Hot Channel Factor shall be within the following limits:

FQ (Z) CFQ

  • K(Z) / P for P > 0.5 FQ (Z) CFQ
  • K(Z) / 0.5 for P 0.5 Where P is the fraction of Rated Power at which the core is operating.

FQ (Z) is both:

  • Steady State FQC(Z) = FQ(Z)
  • 1.08
  • W(Z) / P
  • Rj for P > 0.5 FQW(Z) = FQC(Z)
  • W(Z) / 0.5
  • Rj for P 0.5 CFQ = 2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5A (applicable to Operating Space of Figure 6A), 5B (applicable to Operating Space of Figure 6B) and 5C (applicable to Operating Space of Figure 6A)

Rj is the function in Figures 7A and 7B for the Operating Spaces of Figures 6A and 6B, respectively, and accounts for the potential decrease in transient FQ margin between surveillances.

Figure 8 provides the required limits on THERMAL POWER for the Operating Spaces defined in Figure 8 in the event that additional margin is required.

Applicability: MODE 1 Page 4 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNH) (TS 3.2.2)

The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:

2.7.1 FNH 1.68 X [1 + 0.3(1-P)]

where: P is the fraction of Rated Power at which the core is operating.

Applicability: MODE 1 2.8 Axial Flux Difference (AFD) (TS 3.2.3)

The AFD target band is specified in Figures 6A and 6B.

The AFD Acceptable Operation Limits are provided in Figures 6A and 6B.

Applicability: MODE 1 with THERMAL POWER 15% RTP 2.9 Overtemperature T Setpoint (TS 3.3.1, Table 3.3.1-1 note 1)

Overtemperature T setpoint parameter values (for 1800 MWt core power):

TO = indicated T at RTP, °F T = indicated RCS average temperature, °F T 576.0°F P = pressurizer pressure, psig P 2235 psig K1 1.170 (NTSP)1 K1 1.183 (AV)2 K2 0.016 K3 0.000811 1 = 40 sec 2 = 8 sec 3 = 4 sec 4 = 2 sec for Rosemount RTDs or equivalent 4 0.75 sec for Ultra Electronics RTDs f(I) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RTP, such that:

1 Nominal Setpoint Value 2 Allowable Value Page 5 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 2.9.1 For qt - qb within -12, +6 percent, f(I) = 0.

2.9.2 For each percent that the magnitude of qt - qb exceeds +6 percent, the T trip setpoint shall be automatically reduced by an equivalent of 2.00 percent of Rated Power.

2.9.3 For each percent that the magnitude of qt - qb exceeds -12 percent, the T trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.

Applicability: MODES 1 and 2 2.10 Overpower T Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)

Overpower T setpoint parameter values (for 1800 MWt core power):

TO = indicated T at RTP, °F T = indicated RCS average temperature, °F T 576.0°F K4 1.083 (NTSP)1 K4 1.096 (AV)2 K5 0.0 for increasing T K5 = 0.0 for decreasing T K6 0.00123 for T > T K6 = 0.0 for T < T 5 0 sec 3 = 4 sec 4 = 2 sec for Rosemount RTDs or equivalent 4 0.75 sec for Ultra Electronics RTDs Applicability: MODES 1 and 2 1 Nominal Setpoint Value 2 Allowable Value Page 6 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.11.1 Tavg shall be 577°F.

2.11.2 Pressurizer pressure shall be maintained 2205 psig during operation.

NOTE: Pressurizer pressure limit does not apply during:

1) THERMAL POWER ramp >5% RTP per minute; or
2) THERMAL POWER step >10% RTP.

2.11.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 186,000 gpm.

Applicability: MODE 1 2.12 Refueling Boron Concentration (TS 3.9.1)

Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained 2350 ppm.

Applicability: MODE 6 Page 7 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680 2425 psia 660 2250 psia Unacceptable Operation 640 Highest Loop Average Temperature (°F) 2000 psia 1855 psia 620 Acceptable Operation 600 580 560 540 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 Core Power (fraction of 1800 MWt)

Page 8 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 2 REQUIRED SHUTDOWN MARGIN Page 9 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 3 CONTROL BANK INSERTION LIMITS 240 225 21% 68.50%

210 Bank B Insertion Control Bank Position (Steps Withdrawn) 195 185 180 176 165 Bank C Insertion 150 135 120 105 90 Bank D Insertion 75 60 45 51 30 15 28.50%

0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power Level (% of Rated Power)

NOTE: The Figure is applicable for any fully withdrawn position of 225 steps (Limits are always considered met when withdrawn position is 225 steps).

Page 10 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))

Page 11 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 5A W(Z) function for Operating Space 6A (AFD Band of +/- 5%)

(Top 15% and Bottom 12% Excluded)

W(Z)

Height (feet) 150 1000 2000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 0.2 1.0000 1.0000 1.0000 1.0000 1.0000 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 0.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.2 1.0000 1.0000 1.0000 1.0000 1.0000 1.4 1.0901 1.0895 1.0888 1.0974 1.1051 1.6 1.0910 1.0905 1.0896 1.0976 1.1045 1.8 1.0918 1.0913 1.0905 1.0976 1.1035 2.0 1.0923 1.0919 1.0912 1.0971 1.1020 2.2 1.0925 1.0922 1.0915 1.0962 1.1000 2.4 1.0924 1.0922 1.0917 1.0951 1.0976 2.6 1.0922 1.0920 1.0916 1.0937 1.0950 2.8 1.0918 1.0917 1.0914 1.0920 1.0920 3.0 1.0911 1.0911 1.0909 1.0901 1.0890 3.2 1.0904 1.0903 1.0902 1.0880 1.0858 3.4 1.0894 1.0894 1.0894 1.0856 1.0832 3.6 1.0883 1.0883 1.0884 1.0834 1.0821 3.8 1.0869 1.0869 1.0871 1.0819 1.0816 4.0 1.0854 1.0854 1.0856 1.0810 1.0812 4.2 1.0838 1.0838 1.0840 1.0803 1.0806 4.4 1.0821 1.0821 1.0823 1.0795 1.0803 4.6 1.0804 1.0802 1.0804 1.0789 1.0804 4.8 1.0788 1.0786 1.0785 1.0781 1.0807 5.0 1.0771 1.0769 1.0767 1.0771 1.0809 5.2 1.0752 1.0750 1.0750 1.0760 1.0808 5.4 1.0732 1.0730 1.0730 1.0752 1.0804 5.6 1.0709 1.0707 1.0708 1.0748 1.0796 5.8 1.0685 1.0683 1.0684 1.0742 1.0785 6.0 1.0657 1.0656 1.0658 1.0732 1.0769 Page 12 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 5A (con't)

W(Z) function for Operating Space 6A (AFD Band of +/- 5%)

(Top 15% and Bottom 12% Excluded)

W(Z)

Height (feet) 150 1000 2000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0630 1.0626 1.0629 1.0719 1.0751 6.4 1.0604 1.0596 1.0598 1.0703 1.0726 6.6 1.0582 1.0575 1.0570 1.0683 1.0696 6.8 1.0569 1.0565 1.0560 1.0649 1.0722 7.0 1.0555 1.0553 1.0552 1.0656 1.0766 7.2 1.0545 1.0545 1.0546 1.0703 1.0797 7.4 1.0549 1.0553 1.0557 1.0744 1.0828 7.6 1.0602 1.0606 1.0612 1.0782 1.0854 7.8 1.0659 1.0663 1.0670 1.0819 1.0876 8.0 1.0711 1.0715 1.0725 1.0852 1.0895 8.2 1.0763 1.0767 1.0779 1.0883 1.0910 8.4 1.0814 1.0818 1.0832 1.0910 1.0923 8.6 1.0863 1.0867 1.0883 1.0934 1.0932 8.8 1.0911 1.0914 1.0932 1.0955 1.0937 9.0 1.0955 1.0958 1.0979 1.0973 1.0940 9.2 1.0998 1.1000 1.1023 1.0987 1.0940 9.4 1.1037 1.1039 1.1065 1.0998 1.0937 9.6 1.1073 1.1075 1.1104 1.1006 1.0933 9.8 1.1106 1.1108 1.1140 1.1017 1.0927 10.0 1.1136 1.1138 1.1173 1.1027 1.0919 10.2 1.1162 1.1164 1.1204 1.1034 1.0907 10.4 1.0000 1.0000 1.0000 1.0000 1.0000 10.6 1.0000 1.0000 1.0000 1.0000 1.0000 10.8 1.0000 1.0000 1.0000 1.0000 1.0000 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 11.2 1.0000 1.0000 1.0000 1.0000 1.0000 11.4 1.0000 1.0000 1.0000 1.0000 1.0000 11.6 1.0000 1.0000 1.0000 1.0000 1.0000 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 12.0 1.0000 1.0000 1.0000 1.0000 1.0000 Page 13 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 5B W(Z) function for Operating Space 6B (AFD Band of +/- 3%)

(Top 15% and Bottom 12% Excluded)

W(Z)

Height (feet) 150 1000 2000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 0.2 1.0000 1.0000 1.0000 1.0000 1.0000 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 0.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.2 1.0000 1.0000 1.0000 1.0000 1.0000 1.4 1.0693 1.0688 1.0686 1.0771 1.0728 1.6 1.0687 1.0682 1.0680 1.0774 1.0730 1.8 1.0680 1.0675 1.0673 1.0773 1.0729 2.0 1.0677 1.0673 1.0668 1.0769 1.0723 2.2 1.0677 1.0675 1.0670 1.0760 1.0715 2.4 1.0682 1.0680 1.0676 1.0748 1.0704 2.6 1.0685 1.0683 1.0680 1.0733 1.0690 2.8 1.0685 1.0684 1.0682 1.0716 1.0676 3.0 1.0684 1.0683 1.0682 1.0696 1.0659 3.2 1.0682 1.0681 1.0680 1.0675 1.0641 3.4 1.0677 1.0676 1.0676 1.0651 1.0624 3.6 1.0671 1.0670 1.0670 1.0625 1.0610 3.8 1.0663 1.0662 1.0663 1.0612 1.0610 4.0 1.0653 1.0653 1.0653 1.0610 1.0613 4.2 1.0643 1.0642 1.0643 1.0612 1.0614 4.4 1.0633 1.0632 1.0634 1.0612 1.0616 4.6 1.0623 1.0622 1.0624 1.0611 1.0616 4.8 1.0612 1.0611 1.0612 1.0609 1.0616 5.0 1.0600 1.0598 1.0600 1.0606 1.0614 5.2 1.0587 1.0586 1.0587 1.0602 1.0611 5.4 1.0574 1.0572 1.0573 1.0597 1.0606 5.6 1.0560 1.0558 1.0558 1.0589 1.0599 5.8 1.0546 1.0544 1.0544 1.0580 1.0590 6.0 1.0531 1.0530 1.0530 1.0569 1.0579 Page 14 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 5B (con't)

W(Z) function for Operating Space 6B (AFD Band of +/- 3%)

(Top 15% and Bottom 12% Excluded)

W(Z)

Height (feet) 150 1000 2000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0517 1.0517 1.0516 1.0556 1.0566 6.4 1.0503 1.0503 1.0503 1.0541 1.0549 6.6 1.0488 1.0488 1.0487 1.0522 1.0528 6.8 1.0469 1.0469 1.0469 1.0525 1.0539 7.0 1.0452 1.0451 1.0450 1.0546 1.0562 7.2 1.0429 1.0429 1.0429 1.0572 1.0582 7.4 1.0410 1.0416 1.0421 1.0594 1.0599 7.6 1.0443 1.0449 1.0454 1.0614 1.0615 7.8 1.0481 1.0487 1.0493 1.0632 1.0629 8.0 1.0514 1.0520 1.0527 1.0648 1.0641 8.2 1.0549 1.0555 1.0562 1.0662 1.0651 8.4 1.0584 1.0589 1.0597 1.0674 1.0660 8.6 1.0617 1.0623 1.0631 1.0686 1.0666 8.8 1.0651 1.0656 1.0664 1.0696 1.0671 9.0 1.0683 1.0688 1.0697 1.0704 1.0675 9.2 1.0714 1.0719 1.0728 1.0710 1.0677 9.4 1.0744 1.0748 1.0757 1.0714 1.0678 9.6 1.0772 1.0776 1.0786 1.0718 1.0679 9.8 1.0799 1.0803 1.0812 1.0720 1.0680 10.0 1.0824 1.0828 1.0838 1.0722 1.0682 10.2 1.0848 1.0851 1.0862 1.0721 1.0682 10.4 1.0000 1.0000 1.0000 1.0000 1.0000 10.6 1.0000 1.0000 1.0000 1.0000 1.0000 10.8 1.0000 1.0000 1.0000 1.0000 1.0000 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 11.2 1.0000 1.0000 1.0000 1.0000 1.0000 11.4 1.0000 1.0000 1.0000 1.0000 1.0000 11.6 1.0000 1.0000 1.0000 1.0000 1.0000 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 12.0 1.0000 1.0000 1.0000 1.0000 1.0000 Page 15 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 5C BOC Part-Power W(Z) function for Operating Space 6A (AFD Band of +/- 5%)

(D-Bank 205 steps)

(Top 15% and Bottom 12% Excluded)

Part-Power W(Z) with Correction Factor Height (feet) (excluding power ratio) 75% Power 0.0 1.0000 0.2 1.0000 0.4 1.0000 0.6 1.0000 0.8 1.0000 1.0 1.0000 1.2 1.0000 1.4 1.1722 1.6 1.1688 1.8 1.1661 2.0 1.1625 2.2 1.1582 2.4 1.1539 2.6 1.1497 2.8 1.1452 3.0 1.1400 3.2 1.1348 3.4 1.1294 3.6 1.1241 3.8 1.1185 4.0 1.1130 4.2 1.1083 4.4 1.1042 4.6 1.1004 4.8 1.0960 5.0 1.0906 5.2 1.0845 5.4 1.0784 5.6 1.0722 5.8 1.0659 6.0 1.0591 Page 16 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 5C (con't)

BOC Part-Power W(Z) function for Operating Space 6A (AFD Band of +/- 5%)

(D-Bank 205 steps)

(Top 15% and Bottom 12% Excluded)

Part-Power W(Z) with Correction Factor Height (feet) (excluding power ratio) 75% Power 6.2 1.0524 6.4 1.0460 6.6 1.0400 6.8 1.0347 7.0 1.0292 7.2 1.0242 7.4 1.0210 7.6 1.0228 7.8 1.0249 8.0 1.0262 8.2 1.0274 8.4 1.0289 8.6 1.0307 8.8 1.0324 9.0 1.0338 9.2 1.0354 9.4 1.0371 9.6 1.0394 9.8 1.0421 10.0 1.0452 10.2 1.0484 10.4 1.0000 10.6 1.0000 10.8 1.0000 11.0 1.0000 11.2 1.0000 11.4 1.0000 11.6 1.0000 11.8 1.0000 12.0 1.0000 Page 17 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 6A FLUX DIFFERENCE OPERATING ENVELOPE (AFD Band of +/- 5%)

NOTE:

1. This figure represents the Constant Axial Offset Control (CAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results.

Refer to Figure 2 of Reactor Operating Data (ROD) 1.2 for the administrative limit.

2. The AFD may deviate outside the target band with THERMAL POWER < 50% RTP.
3. The AFD target band is +/-5% for THERMAL POWER 15% RTP.

Page 18 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 6B FLUX DIFFERENCE OPERATING ENVELOPE (AFD Band of +/- 3%)

NOTE:

1. This figure represents the Constant Axial Offset Control (CAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results.

Refer to Figure 2 of Reactor Operating Data (ROD) 1.2 for the administrative limit.

2. The AFD may deviate outside the target band with THERMAL POWER < 50% RTP.
3. The AFD target band is +/-3% for THERMAL POWER 15% RTP.

Page 19 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 FIGURE 7A (AFD Band of +/- 5%)

Cycle Burnup Rj (MWD/MTU)

BOL to 1252 1.025 1253 to EOL 1.020 The Figure 7A Rj margin decrease factors for Operating Space 6A are applicable.

FIGURE 7B (AFD Band of +/- 3%)

Cycle Burnup Rj (MWD/MTU)

BOL to 1068 1.025 1069 to EOL 1.020 The Figure 7B Rj margin decrease factors for Operating Space 6B are applicable.

FIGURE 8. REQUIRED THERMAL POWER LIMITS Required FQW(Z) Margin Required THERMAL CAOC Operating Space Improvement (%) POWER limit (% RTP) 1.8 98 Figure 6A

> 1.8 <50 2.0 98 Figure 6B

> 2.0 <50 Page 20 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section All Reactor Thermal Output Caldon, Inc., Engineering Report-80P, TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM' System, Revision 0, Mar 1997.

Caldon, Inc., Engineering Report-160P, Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM' System, Revision 0, May 2000.

WCAP-12610-P-A, VANTAGE+ Fuel Assembly Fuel Assembly Reference Core Report, April 1995.

WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, Optimized ZIRLOTM, July 2006.

2.1 Reactor Core Safety Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

2.2 Shutdown Margin WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

2.3 Moderator Temperature WCAP-9272-P-A, "Westinghouse Reload Safety Coefficient Evaluation Methodology," July 1985.

2.4 Shutdown Bank Insertion Limit WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

2.5 Control Bank Insertion Limits WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

2.6 Nuclear Heat Flux Hot WCAP-8403 (non-proprietary), Power Distribution Channel Factor (FQ(Z)) Control and Load Following Procedures, Westinghouse Electric Corporation, September 1974.

WCAP-14449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision 1, October 1999 (cores containing 422V + fuel).

WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.

WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

WCAP-10054-P-A, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," Addendum 2, Revision 1, July 1997.

Page 21 of 22

POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 23 March 18, 2023 CORE OPERATING LIMITS REPORT (COLR)

UNIT 2 CYCLE 40 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot WCAP-9272-P-A, "Westinghouse Reload Safety Channel Factor (FNH) Evaluation Methodology," July 1985.

WCAP-16259-P-A, Westinghouse Methodology for Applications of 3-D Transient Neutronics to Non-LOCA Accident Analysis, August 2006.

2.8 Axial Flux Difference (AFD) WCAP-8403 (nonproprietary), Power Distribution Control and Load Following Procedures, Westinghouse Electric Corporation, September 1974.

NS-TMA-2198, Westinghouse to NRC Letter

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package, January 31, 1980.

NS-CE-687, Westinghouse to NRC Letter, Power Distribution Control Analysis, July 16, 1975.

2.9 Overtemperature T Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions," September 1986 2.10 Overpower T Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions," September 1986 2.11 RCS Pressure, Temperature, WCAP-11397-P-A, "Revised Thermal Design and Flow Departure from Procedure," April 1989, for those events analyzed Nucleate Boiling (DNB) Limits using RTDP WCAP-14787-P, Rev. 3, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Point Beach Units 1 & 2 Power Uprate (1775 MWt Core Power with Feedwater Venturis, or 1800 MWt Core Power with LEFM on Feedwater Header)", February 2009.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP 2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Page 22 of 22

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