Revision as of 09:12, 7 May 2019

Text

Core Operating Limits Report (COLR) Unit 2 Cycle 35 (U2C35) and Correction to Unit 1 Cycle 36 (U1C36)
	ML15308A097
Person / Time
Site:	Point Beach
Issue date:	11/04/2015
From:	Woyak B; Point Beach
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC 2015-0067
	Download: ML15308A097 (39)
	v • d • e

November 4, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Units 1 and 2 Docket No. 50-266 and 50-301 Renewed License No. DPR-24 and DPR-27 Core Operating Limits Report (COLR) Unit 2 Cycle 35 (U2C35) and Correction to Unit 1 Cycle 36 (U1 C36) In accordance with the requirements of Point Beach Nuclear Plant (PBNP) NRC 2015-0067 TS 5.6.4 Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 2, Cycle 35 and a correction to TRM 2.1, COLR Unit 1 Cycle 36 (U1C36). Enclosure 1 to this letter contains the PBNP U2C35 COLR that was issued on October 15, 2015. Enclosure 2 to this letter contains a revised U 1 C36 COLR to correct Figure 2. It was identified that the numeric values in Figure 2 did not display properly.

This letter contains no new regulatory commitments and no revisions to existing commitments.

Very truly yours, NextEra Energy Point Beach, LLC Bryan Woyak Licensing Manager Enclosures cc: Administrator, Region Ill, 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 ENCLOSURE1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 2 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 (U1C35) 18 pages follow TRM 2.1 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 REVISION 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 18 October 15, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 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 (F 0 (Z)) 2.7 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN 11 H) 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature L1 T Setpoint 2.10 3.3.1 Overpower L1 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)) for 422V+ Fuel Figure 5 3.2.1 Summary of W(Z) as a Function of Core Height Figure 5A 3.2.1 BOG Part-Power Summary of W(Z) as a Function of Core Height Figure 6 3.2.3 Flux Difference Operating Envelope Table 1 5.6.4 NRC Approved Methodologies for COLR Parameters Page 2 of 18 POl NT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 2.0 OPERATING LIMITS TRM 2.1 U2 Revision 18 October 15, 2015 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% .b.klk (see Figure 2). Applicability:

MODES 1, 2, and 3 2.2.2 SDM shall be ;::::1% Aklk. 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: pcmrF for power levels RTP pcmrF for power levels > 70% RTP Applicability:

MODE 1 and MODE 2 with keff 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 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 2.5 Control Bank Insertion Limits (TS 3.1.6) TRM 2.1 U2 Revision 18 October 15, 2015 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. Applicability:

MODE 1 and MODE 2 with keff <::1.0 2.6 Nuclear Heat Flux Hot Channel Factor (F 0 (Z)) (TS 3.2.1) The Heat Flux Hot Channel Factor shall be within the following limits: Fa (Z)::; CFQ

K(Z) I P Fa (Z) ::; CFQ

K(Z) I 0.5 for P > 0.5 for P::; 0.5 Where Pis the fraction of Rated Power at which the core is operating.

Fa (Z) is both:

Steady State Fa c(Z) = Fa(Z)

1.08

Transient Faw(Z) = Fac(Z)

W(Z) I P for P > 0.5 Fa w(Z) = Fa c(Z)

W(Z) I 0.5 for P ::; 0.5 CFa = 2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and 5A The following FQ penalty factors are applicable to Cycle 35. Cycle Burnup Fvv 0 (Z) Penalty (MWD/MTU)

Factors BOL to 1179 1.026 1179 to EOL 1.02 Applicability:

MODE 1 Page 4 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 2. 7 Nuclear Enthalpy Rise Hot Channel Factor !lli) (TS 3.2.2) TRM 2.1 U2 Revision 18 October 15, 2015 The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: 2.7.1 FNAH<1.68X[1

+0.3(1-P)]

where: Pis 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 +/-5%. The AFD Acceptability Operation Limits are provided in Figure 6. Applicability:

MODE 1 with THERMAL POWER >15% RTP 2.9 OvertemperatureilT Setpoint (TS 3.3.1, Table 3.3.1-1 note 1) Overtemperature L1 T setpoint parameter values (for 1800 MWt core power): L1To = indicated L1T at RTP, oF T = indicated RCS average temperature, oF T' ::::; 576.0°F p = pressurizer pressure, psig P' ::::: 2235 psig K1 ::::; 1.175 (NTSP)1 K1 ::::; 1.188 (AV)2 Kz ::::: 0.016 K3 ::::: 0.000811 1:1 = 40 sec 1:z = 8 sec 1:3 = 4 sec 1:4 = 2 sec f(ill) 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 q and qb are the percent power in the top and bottom halves of the core respectively, and q + qb is total core power in percent of RTP, such that: 1 Nominal Setpoint Value 2 Allowable Value Page 5 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 2.9.1 For q 1-qb within -12, +6 percent, f(ill) = 0. TRM 2.1 U2 Revision 18 October 15, 2015 2.9.2 For each percent that the magnitude of%-qb exceeds +6 percent, the ilT 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 q 1-qb exceeds -12 percent, the ilT trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power. Applicability:

MODES 1 and 2 2.10 Overpower L1 T Setpoint (TS 3.3.1, Table 3.3.1-1 note 2) Overpower L1 T setpoint parameter values (for 1800 MWt core power): ilTo = indicated ilT at RTP, oF T = indicated RCS average temperature, oF T' ::::; 576.0°F ::::; 1.098 (NTSP)1 ::::; 1.111 (AV)2 Ks 2': 0.0 for increasing T Ks = 0.0 for decreasing T K6 2': 0.00123 T' K6 = 0.0 forT< T' 'ts 2': 0 sec 't3 = 4 sec 't4 = 2 sec Applicability:

MODES 1 and 2 1 Nominal Setpoint Value 2 Allowable Value Page 6 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 TRM 2.1 U2 Revision 18 October 15, 2015 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling CDNB) Limits (TS 3.4.1) 2.11.1 2.11.2 2.11.3 Tavg shall be ::;;57rF.

Pressurizer pressure shall be maintained

2:2205 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. Reactor Coolant System raw measured Total Flow Rate shall be maintained

2:186,000 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 ppm. Applicability:

MODE 6 Page 7 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE TRM 2.1 U2 Revision 18 October 15, 2015 Unacceptable Operation 0.0 0.2 0.4 0.6 0.8 1.0 Core Power (fraction of 1800 MWt) Page 8 of 18 1.2 1.4

& <..< "' <II ::: '"' ::E ;; 0 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE 2 REQUIRED SHUTDOWN MARGIN TRM 2.1 U2 Revision 18 October 15, 2015 :>.o% I I I I I I I I I I I 2.5% 2.0'16 1.5% 1.0%

I I . I I , I I I I I I I 0.0% Q 10 20 30 40 50 60 70 80 90 10.0 Cm e Bum up (%) Page 9 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 18 October 15, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 ...........

c :5: co L-"0 ..c ...... en 0.. (l) ...... CJ) '-" c 0 +=i *en 0 0.. .::£ c co co 0 L-...... c 0 0 240 225 210 195 180 165 150 135 120 105 90 75 60 45 30 15 0 FIGURE 3 CONTROL BANK INSERTION LIMITS I 121% I / 168.50% I / v *1 Bank B Insertion

/ / v / / 18}]-/ v / / I 176l / / v 1 Bank C Insertion 1 / // / v / / v / / / / / "I Bank D Insertion -/ / / /v / v / /v / I 28.50% V / I .A' 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 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE 4 TRM 2.1 U2 Revision 18 October 15, 2015 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) 1.2 j<o.ot l.o)J I (6.0, l.O)j 11 (12.0, 1.0) 1 0.9 0.8 I 0.7 0.5 0.4 0.3 0.2 0.1 0 I 0 l 2 3 4 5 6 7 8 9 10 11 CORE HEIGHT (Fl) Page 11 of 18 12 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE 5 TRM 2.1 U2 Revision 18 October 15, 2015 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

Height W(Z) {feet) 150 3000 8000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.0 1.0000 1.0000 1.0000 1.0000 0.2 1.0000 1.0000 1.0000 1.0000 0.4 1.0000 1.0000 1.0000 1.0000 0.6 1.0000 1.0000 1.0000 1.0000 0.8 1.0000 1.0000 1.0000 1.0000 1.0 1.0000 1.0000 1.0000 1.0000 1.2 1.0000 1.0000 1.0000 1.0000 1.4 1.0000 1.0000 1.0000 1.0000 1.6 1.0972 1.0983 1.1075 1.1222 1.8 1.0973 1.0983 1.1066 1.1195 2.0 1.0970 1.0980 1.1053 1.1162 2.2 1.0965 1.0973 1.1036 1.1124 2.4 1.0958 1.0964 1.1015 1.1080 2.6 1.0949 1.0953 1.0990 1.1032 2.8 1.0937 1.0939 1.0963 1.0980 3.0 1.0923 1.0921 1.0931 1.0921 3.2 1.0906 1.0906 1.0900 1.0877 3.4 1.0892 1.0895 1.0873 1.0852 3.6 1.0886 1.0883 1.0857 1.0826 3.8 1.0884 1.0869 1.0844 1.0822 4.0 1.0882 1.0858 1.0837 1.0826 4.2 1.0879 1.0851 1.0834 1.0834 4.4 1.0874 1.0840 1.0828 1.0842 4.6 1.0867 1.0828 1.0821 1.0848 4.8 1.0857 1.0814 1.0812 1.0852 5.0 1.0844 1.0798 1.0803 1.0853 5.2 1.0829 1.0781 1.0794 1.0851 5.4 1.0811 1.0763 1.0785 1.0846 5.6 1.0790 1.0743 1.0773 1.0837 5.8 1.0766 1.0721 1.0758 1.0824 6.0 1.0739 1.0696 1.0739 1.0805 Page 12 of 18 I POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE 5 (con't) TRM 2.1 U2 Revision 18 October 15, 2015 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

W(Z) Height (feet) 150 3000 8000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0709 1.0668 1.0718 1.0784 6.4 1.0679 1.0642 1.0700 1.0755 6.6 1.0650 1.0621 1.0685 1.0717 6.8 1.0622 1.0608 1.0659 1.0736 7.0 1.0600 1.0597 1.0661 1.0777 7.2 1.0578 1.0596 1.0702 1.0808 7.4 1.0570 1.0621 1.0747 1.0837 7.6 1.0620 1.0673 1.0789 1.0861 7.8 1.0678 1.0725 1.0829 1.0882 8.0 1.0730 1.0776 1.0865 1.0900 8.2 1.0784 1.0828 1.0897 1.0914 8.4 1.0838 1.0877 1.0926 1.0925 8.6 1.0892 1.0924 1.0952 1.0937 8.8 1.0943 1.0967 1.0973 1.0949 9.0 1.0991 1.1007 1.0991 1.0959 9.2 1.1035 1.1043 1.1004 1.0965 9.4 1.1075 1.1075 1.1014 1.0969 9.6 1.1117 1.1109 1.1023 1.0968 9.8 1.1158 1.1141 1.1034 1.0965 10.0 1.1196 1.1169 1.1044 1.0958 10.2 1.1230 1.1193 1.1052 1.0946 10.4 1.0000 1.0000 1.0000 1.0000 10.6 1.0000 1.0000 1.0000 1.0000 10.8 1.0000 1.0000 1.0000 1.0000 11.0 1.0000 1.0000 1.0000 1.0000 11.2 1.0000 1.0000 1.0000 1.0000 11.4 1.0000 1.0000 1.0000 1.0000 11.6 1.0000 1.0000 1.0000 1.0000 11.8 1.0000 1.0000 1.0000 1.0000 12.0 1.0000 1.0000 1.0000 1.0000 Page 13 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 18 October 15, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE SA BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

Part-Power W(Z) with Correction Factor Height (feet) (excluding

!)ower ratio) Hot Full Power 75% Power 0.0 1.0000 1.0000 0.2 1.0000 1.0000 0.4 1.0000 1.0000 0.6 1.0000 1.0000 0.8 1.0000 1.0000 1.0 1.0000 1.0000 1.2 1.0000 1.0000 1.4 1.0000 1.0000 1.6 1.0972 1.1828 1.8 1.0973 1.1790 2.0 1.0970 1.1745 2.2 1.0965 1.1694 2.4 1.0958 1.1639 2.6 1.0949 1.1583 2.8 1.0937 1.1525 3.0 1.0923 1.1467 3.2 1.0906 1.1406 3.4 1.0892 1.1348 3.6 1.0886 1.1296 3.8 1.0884 1.1248 4.0 1.0882 1.1214 4.2 1.0879 1.1178 4.4 1.0874 1.1136 4.6 1.0867 1.1087 4.8 1.0857 1.1035 5.0 1.0844 1.0982 5.2 1.0829 1.0926 5.4 1.0811 1.0866 5.6 1.0790 1.0802 5.8 1.0766 1.0734 6.0 1.0739 1.0662 Page 14 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 18 October 15, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE SA (con't) BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

Part-Power W(Z) with Correction Factor Height (feet) (excluding flOWer ratio) Hot Full Power 75% Power 6.2 1.0709 1.0589 6.4 1.0679 1.0515 6.6 1.0650 1.0444 6.8 1.0622 1.0373 7.0 1.0600 1.0309 7.2 1.0578 1.0245 7.4 1.0570 1.0198 7.6 1.0620 1.0204 7.8 1.0678 1.0219 8.0 1.0730 1.0227 8.2 1.0784 1.0237 8.4 1.0838 1.0246 8.6 1.0892 1.0257 8.8 1.0943 1.0266 9.0 1.0991 1.0274 9.2 1.1035 1.0282 9.4 1.1075 1.0290 9.6 1.1117 1.0303 9.8 1.1158 1.0318 10.0 1.1196 1.0335 10.2 1.1230 1.0357 10.4 1.0000 1.0000 10.6 1.0000 1.0000 10.8 1.0000 1.0000 11.0 1.0000 1.0000 11.2 1.0000 1.0000 11.4 1.0000 1.0000 11.6 1.0000 1.0000 11.8 1.0000 1.0000 12.0 1.0000 1.0000 Page 15 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 FIGURE 6 TRM 2.1 U2 Revision 18 October 15, 2015 FLUX DIFFERENCE OPERATING ENVELOPE 40 NOTE: tiNA C:C;EPTAB LE OPEF!ATIDN 30 *20 i\CCEPTA6LE OPERATION 0 0 10 Axial Fhxx Difference PCVA;;f Enve!cpe lLO 11.0 11:'1-C 2L:J 21.0 .. 25J1 3LG 3LO UNACCEPfAHLE OPERATJON 30 40 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 15% RTP. Page 16 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 18 October 15, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section All Reactor Thermal Output Caldon, Inc., Engineering Report-BOP, "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM"Ž System," Revision 0, Mar 1997. Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM"Ž System," Revision 0, May 2000. Fuel Assembly WCAP-12610-P-A, "VANTAGE+

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

& CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOŽ," 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 (F 0 (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-1 0054-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 17 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 18 October 15, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 35 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 (FN t.H) 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 11 T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower 11 T and Thermal Overtemperature 11 T Trip Functions," September 1986 2.10 Overpower 11 T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower 11 T and Thermal Overtemperature 11 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 18 of 18 ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 (U1C36) (Revision

17) 18 pages follow TRM 2.1 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 REVISION 17 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 17 October 26, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 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 Section 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure SA Figure 6 Table 1 PBNP TS 2.1.1 3.1.1 3.1.4 3.1.5 3.1.6 3.1.8 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 3.3.1 3.3.1 3.4.1 3.9.1 2.1.1 3.1.1 3.1.6 3.2.1 3.2.1 3.2.1 3.2.3 5.6.4 Description Reactor Core Safety Limits Shutdown Margin Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits Physics Test Exceptions Moderator Temperature Coefficient Shutdown Bank Insertion Limit Control Bank Insertion Limits Nuclear Heat Flux Hot Channel Factor (F 0 (Z)) Nuclear Enthalpy Rise Hot Channel Factor (FN t-H) Axial Flux Difference (AFD) Overtemperature T Setpoint Overpower T Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Refueling Boron Concentration Reactor Core Safety Limits Curve Required Shutdown Margin Control Bank Insertion Limits Hot Channel Factor Normalized Operating Envelope (K(Z)) Summary of W(Z) as a Function of Core Height SOC Part-Power Summary of W(Z) as a Function of Core Height Flux Difference Operating Envelope NRC Approved Methodologies for COLR Parameters Page 2 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 2.0 OPERATING LIMITS TRM 2.1 U1 Revision 17 October 26, 2015 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':2.0% t1k/k (see Figure 2). Applicability:

MODES 1 , 2, and 3 2.2.2 SDM shall be 2':1% t1klk. 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: pcm/°F for power levels RTP pcm/°F for power levels > 70% RTP Applicability:

MODE 1 and MODE 2 with keff 2':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 2': 225 steps. Applicability:

MODES 1 and 2 Page 3 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 2.5 Control Bank Insertion Limits (TS 3.1.6) TRM 2.1 U1 Revision 17 October 26, 2015 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. Applicability:

MODE 1 and MODE 2 with kett 21.0 2.6 Nuclear Heat Flux Hot Channel Factor (Fo(Z)) (TS 3.2.1) The Heat Flux Hot Channel Factor shall be within the following limits: Fa(Z) CFa

K(Z) I P for P > 0.5 Fa(Z) CFa

K(Z) I 0.5 for P 0.5 Where Pis the fraction of Rated Power at which the core is operating.

Fa(Z) is both:

Steady State

Transient CFa = 2.60 Fa c(Z) = Fa(Z)

1.08 Faw(Z) = Fac(Z)

W(Z) I P for P>0.5 Fa w(Z) = Fa c(Z)

W(Z) I 0.5 for P_::: 0.5 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and SA. The following Fa penalty factors are applicable to Cycle 36. Cycle Burn up Fw Q{Z) Penalty (MWD/MTU)

Factors BOLto 1325 1.027 1326 to EOL 1.02 Applicability:

MODE 1 Page 4 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 TRM 2.1 U1 Revision 17 October 26, 2015 2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN .6!::!) (TS 3.2.2) The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: 2.7.1 FNAH:::::1.68x[1

+0.3(1-P)]

where: Pis 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 +/-5%. The AFD Acceptability Operation Limits are provided in Figure 6. Applicability:

MODE 1 with THERMAL POWER :2:15% RTP Page 5 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 TRM 2.1 U1 Revision 17 October 26, 2015 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): = indicated RTP, oF T = indicated RCS average temperature, oF T' ::::; 576.0°F p = pressurizer pressure, psig P' 2235 psig K1 ::::; 1.175 (NTSP)1 K1 ::::; 1.188 (AVf Kz 0.016 K3 0.000811 't1 = 40 sec 'tz = 8 sec 't3 = 4 sec 't4 = 2 sec is an even 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: 2.9.1 For qt-qb within -12, +6 percent,

= 0. 2.9.2 For each percent that the magnitude of%-qb exceeds +6 percent, 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 trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power. 1 Nominal Setpoint Value 2 Allowable Value Applicability:

MODES 1 and 2 Page 6 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 17 October 26, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 2.10 Overpower ilT Setpoint (TS 3.3.1. Table 3.3.1-1 note 2) Overpower il T setpoint parameter values (for 1800 MWt core power): ilTo = indicated il Tat RTP, oF T = indicated RCS average temperature, oF T' ::::; 576.0°F ::::; 1. 098 (NTSP) 1 ::::; 1.111 (AVf Ks = 0.0 for increasing T Ks = 0.0 for decreasing T Ke 0.00123 T' Ke = 0.0 forT< T' Ts = 0 sec TJ = 4 sec 't4 = 2 sec Applicability:

MODES 1 and 2 2.11 RCS Pressure.

Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.11.1 2.11.2 2.11.3 Tavg shall be ::::;577°F.

Pressurizer pressure shall be maintained 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. Reactor Coolant System raw measured Total Flow Rate shall be maintained 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 ppm. Applicability:

MODE 6 1 Nominal Setpoint Value 2 Allowable Value Page 7 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE 1 TRM 2.1 U1 Revision 17 October 26, 2015 REACTOR CORE SAFETY LIMITS CURVE Unacceptable Operation 0.0 0.2 0.4 0.6 0.8 1.0 Core Power (fraction of 1800 MWt) Page 8 of 18 1.2 1.4 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE 2 REQUIRED SHUTDOWN MARGIN TRM 2.1 U1 Revision 17 October 26, 2015 3.,5% I I I I I I I :w, I I ,___, 3.0% -+-+-'i-H--+-\-:

-H-H-:-HH 2.5% t l ! I I "' :E 1.5% -:s :::; .!: Vl =i 1.0% -+-',--H--+-\-i 0.5% +-+-: I ._....._,__;

I :-H-:-H....._,_:

0.0% 0 10 20 30 40 50 GO 70 80 90 100 Core Burn up(%) Page 9 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 17 October 26, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 ..........

c :s: ro .._ "0 ..c (/) a. Q) ....... (f) ---c 0 :e (/) 0 0... c ro ro 0 .._ ....... c 0 0 240 225 210 195 180 165 150 135 120 105 90 75 60 45 30 15 0 FIGURE 3 CONTROL BANK INSERTION LIMITS I I I 121% L / 168.50% I / v 'i Bank B Insertion i / / / / 18I} / I" / I 1761 / / / 1 Bank C Insertion 1 v /"' / / / / v / / / v / ""I Bank D Insertion -/ // / / v / / / 1 28.50% I/ v I I X 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 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE 4 TRM 2.1 U1 Revision 17 October 26, 2015 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) 1.2 1.1 1 1(0.0, 1.0)1 1(6.0, 1.0)1 11 (12.0, 1.0} 0.9 0.8 0.7 N' '-' 0.6 0.5 0.4 0.3 0.2 0.1 0 0 1 2 3 4 s 6 7 8 9 10 11 CORE HEIGHT (FI) Page 11 of 18 12 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE 5 TRM 2.1 U1 Revision 17 October 26, 2015 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

WZ) Height (feet) 150 3000 8000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.0 1.0000 1.0000 1.0000 1.0000 0.2 1.0000 1.0000 1.0000 1.0000 0.4 1.0000 1.0000 1.0000 1.0000 0.6 1.0000 1.0000 1.0000 1.0000 0.8 1.0000 1.0000 1.0000 1.0000 1.0 1.0000 1.0000 1.0000 1.0000 1.2 1.0000 1.0000 1.0000 1.0000 1.4 1.0000 1.0000 1.0000 1.0000 1.6 1.0986 1.0999 1.1089 1.1218 1.8 1.0986 1.0998 1.1079 1.1190 2.0 1.0982 1.0994 1.1064 1.1156 2.2 1.0975 1.0986 1.1045 1.1117 2.4 1.0966 1.0976 1.1023 1.1072 2.6 1.0955 1.0963 1.0997 1.1023 2.8 1.0941 1.0947 1.0967 1.0971 3.0 1.0925 1.0929 1.0933 1.0917 3.2 1.0906 1.0908 1.0901 1.0876 3.4 1.0889 1.0888 1.0876 1.0850 3.6 1.0883 1.0880 1.0861 1.0829 3.8 1.0881 1.0875 1.0847 1.0830 4.0 1.0879 1.0868 1.0834 1.0835 4.2 1.0874 1.0859 1.0826 1.0837 4.4 1.0867 1.0849 1.0823 1.0838 4.6 1.0858 1.0837 1.0817 1.0837 4.8 1.0846 1.0823 1.0810 1.0834 5.0 1.0833 1.0808 1.0801 1.0828 5.2 1.0817 1.0792 1.0789 1.0820 5.4 1.0798 1.0773 1.0775 1.0808 5.6 1.0779 1.0751 1.0758 1.0794 5.8 1.0757 1.0727 1.0741 1.0775 6.0 1.0731 1.0700 1.0723 1.0753 Page 12 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE 5 (con't) TRM 2.1 U1 Revision 17 October 26, 2015 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

WZ) Height (feet) 150 3000 8000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0702 1.0670 1.0708 1.0723 6.4 1.0669 1.0641 1.0699 1.0696 6.6 1.0641 1.0622 1.0686 1.0708 6.8 1.0619 1.0613 1.0659 1.0738 7.0 1.0605 1.0604 1.0672 1.0772 7.2 1.0590 1.0606 1.0723 1.0801 7.4 1.0584 1.0636 1.0764 1.0827 7.6 1.0633 1.0689 1.0803 1.0849 7.8 1.0692 1.0742 1.0840 1.0868 8.0 1.0745 1.0791 1.0872 1.0883 8.2 1.0799 1.0840 1.0902 1.0894 8.4 1.0851 1.0885 1.0928 1.0903 8.6 1.0900 1.0927 1.0950 1.0912 8.8 1.0946 1.0966 1.0968 1.0921 9.0 1.0989 1.1002 1.0983 1.0928 9.2 1.1029 1.1034 1.0994 1.0933 9.4 1.1065 1.1061 1.1001 1.0936 9.6 1.1097 1.1090 1.1010 1.0941 9.8 1.1132 1.1119 1.1015 1.0945 10.0 1.1167 1.1144 1.1018 1.0948 10.2 1.1197 1.1165 1.1033 1.0948 10.4 1.0000 1.0000 1.0000 1.0000 10.6 1.0000 1.0000 1.0000 1.0000 10.8 1.0000 1.0000 1.0000 1.0000 11.0 1.0000 1.0000 1.0000 1.0000 11.2 1.0000 1.0000 1.0000 1.0000 11.4 1.0000 1.0000 1.0000 1.0000 11.6 1.0000 1.0000 1.0000 1.0000 11.8 1.0000 1.0000 1.0000 1.0000 12.0 1.0000 1.0000 1.0000 1.0000 Page 13 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 17 October 26, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE SA BOC Part-Power Summary of W(Z) as a Function of Core Height (D-Bank:::::;

205 steps) (Top 15% and Bottom 12% Excluded)

Part-Power W(Z) with Correction Factor Height (feet) (excluding iJOWer ratio) Hot Full Power 75% Power 0.0 1.0000 1.0000 0.2 1.0000 1.0000 0.4 1.0000 1.0000 0.6 1.0000 1.0000 0.8 1.0000 1.0000 1.0 1.0000 1.0000 1.2 1.0000 1.0000 1.4 1.0000 1.0000 1.6 1.0986 1.1882 1.8 1.0986 1.1844 2.0 1.0982 1.1793 2.2 1.0975 1.1733 2.4 1.0966 1.1672 2.6 1.0955 1.1611 2.8 1.0941 1.1547 3.0 1.0925 1.1481 3.2 1.0906 1.1412 3.4 1.0889 1.1346 3.6 1.0883 1.1292 3.8 1.0881 1.1241 4.0 1.0879 1.1190 4.2 1.0874 1.1136 4.4 1.0867 1.1086 4.6 1.0858 1.1046 4.8 1.0846 1.1008 5.0 1.0833 1.0968 5.2 1.0817 1.0919 5.4 1.0798 1.0858 5.6 1.0779 1.0789 5.8 1.0757 1.0718 6.0 1.0731 1.0647 Page 14 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 17 October 26, 2015 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE SA (can't) BOC Part-Power Summary of W(Z) as a Function of Core Height (D-Bank 205 steps) (Top 15% and Bottom 12% Excluded)

Part-Power W(Z) with Correction Factor Height (feet) (excluding ower ratio) Hot Full Power 75% Power 6.2 1.0702 1.0576 6.4 1.0669 1.0500 6.6 1.0641 1.0427 6.8 1.0619 1.0359 7.0 1.0605 1.0299 7.2 1.0590 1.0237 7.4 1.0584 1.0185 7.6 1.0633 1.0188 7.8 1.0692 1.0200 8.0 1.0745 1.0209 8.2 1.0799 1.0219 8.4 1.0851 1.0228 8.6 1.0900 1.0234 8.8 1.0946 1.0236 9.0 1.0989 1.0240 9.2 1.1029 1.0240 9.4 1.1065 1.0240 9.6 1.1097 1.0241 9.8 1.1132 1.0251 10.0 1.1167 1.0266 10.2 1.1197 1.0282 10.4 1.0000 1.0000 10.6 1.0000 1.0000 10.8 1.0000 1.0000 11.0 1.0000 1.0000 11.2 1.0000 1.0000 11.4 1.0000 1.0000 11.6 1.0000 1.0000 11.8 1.0000 1.0000 12.0 1.0000 1.0000 Page 15 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 FIGURE 6 TRM 2.1 U1 Revision 17 October 26, 2015 FLUX DIFFERENCE OPERATING ENVELOPE Po\ver Tech Spe-c NOTES: 90 85 70 65 60 55 50. -*40 I I I' LINACCE::PT ABLE 1. OPERATION

/ / / f I I I I l I f / l ! 20 ACCEPTABLE 0 10 Axial Flux Difference Level Envelc*ce %r , .*j 1.0 "11 .'!"'>.,. .i.i' *1B.G l6.& 7{} -2'1.=0 2"1 .fi 6-G -2fi.:Q. 2.8*.0 -31.D 31 '"'* .u 20 30 40 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 16 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 TABLE 1 TRM2.1 U1 Revision 17 October 26, 2015 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section All Reactor Thermal Output Caldon, Inc., Engineering Report-BOP, "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM"Ž System," Revision 0, Mar 1997. Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM"Ž System," Revision 0, May 2000. 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 Coefficient WCAP-9272-P-A, "Westinghouse Reload Safety 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 Channel WCAP-8403 (non-proprietary), "Power Factor (F 0 (Z)) Distribution Control and Load Following Procedures," 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-1 0054-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 17 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 36 COLR Parameter Section 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN L>H) 2.8 Axial Flux Difference (AFD) 2.9 Overtemperature L1 T Setpoint 2.10 Overpower L1 T Setpoint 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration TRM 2.1 U1 Revision 17 October 26, 2015 NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985. WCAP-16259-P-A, "Westinghouse Methodology for Applications of 3-D Transient Neutronics to Non-LOCA Accident Analysis," August 2006. WCAP-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," September 197 4. 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. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower L1 T and Thermal Overtemperature L1 T Trip Functions," September 1986. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower L1 T and Thermal Overtemperature L1 T Trip Functions," September 1986. WCAP-11397 -P-A, "Revised Thermal Design Procedure," April 1989, for those events analyzed 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. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985. Page 18 of 18 November 4, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Units 1 and 2 Docket No. 50-266 and 50-301 Renewed License No. DPR-24 and DPR-27 Core Operating Limits Report (COLR) Unit 2 Cycle 35 (U2C35) and Correction to Unit 1 Cycle 36 (U1 C36) In accordance with the requirements of Point Beach Nuclear Plant (PBNP) NRC 2015-0067 TS 5.6.4 Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 2, Cycle 35 and a correction to TRM 2.1, COLR Unit 1 Cycle 36 (U1C36). Enclosure 1 to this letter contains the PBNP U2C35 COLR that was issued on October 15, 2015. Enclosure 2 to this letter contains a revised U 1 C36 COLR to correct Figure 2. It was identified that the numeric values in Figure 2 did not display properly.