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Text

Core Operating Limits Report (COLR) Cycle 37 (U1C37)
	ML16089A075
Person / Time
Site:	Point Beach
Issue date:	03/29/2016
From:	Woyak B; Point Beach
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC 2016-0011 U1C37
	Download: ML16089A075 (20)
	v • d • e

March 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 1 Docket No. 50-266 Renewed License No. DPR-24 Core Operating Limits Report (COLR) Unit 1 Cycle 37 (U1C37) In accordance with the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 1, Cycle 37. NRC 2016-0011 TS 5.6.4 The Enclosure to this letter contains the PBNP U1C37 COLR that was issued on March 19, 2016. This letter contains no new regulatory commitments and no revisions to existing commitments.

Sincerely, NextEra Energy Point Beach, LLC Bryan Woyak Licensing Manager Enclosure 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, Wl54241 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 (U1C37) ' ,*, 'i 18 pages follow TRM 2.1 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 REVISION 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 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 5A Figure 6 Table 1 PBNP Description TS 2.1.1 Reactor Core Safety Limits 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 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 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 llH) Axial Flux Difference (AFD) Overtemperature L1 T Setpoint Overpower L1 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 BOC 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 37 2.0 OPERATING LIMITS TRM 2.1 U1 Revision 18 March 19, 2016 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 (see Figure 2). Applicability:

MODES 1, 2, and 3 2.2.2 SDM shall be :::::1%

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 kett :::::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 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 2.5 Control Bank Insertion Limits (TS 3.1.6) TRM 2.1 U1 Revision 18 March 19, 2016 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: F 0 (Z) CF 0

K(Z) I P F 0 (Z) CF 0

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

F 0 (Z) is both:

Steady State

Transient CF 0 = 2.60 F 0 c(Z) = Fo(Z)

1.08 F 0 w(Z) = F 0 c(Z)

W(Z) I P for P>0.5 F 0 w(Z) = F 0 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 F 0 penalty factors are applicable to Cycle 37. Cycle Burnup Fw 0 (Z) Penalty (MWD/MTU)

Factors BOL 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 37 TRM 2.1 U1 Revision 18 March 19, 2016 2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN AH) (TS 3.2.2) The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: 2. 7.1 FN 8H :::;1.68 X [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 RTP Page 5 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 TRM 2.1 U1 Revision 18 March 19, 2016 2.9 Overtemperature L1T Setpoint CTS 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 K2 ;;::: 0.016 K3 ;;::: 0.000811 'L1 = 40 sec 'L2 = 8 sec 'L3 = 4 sec 'L4 = 2 sec f(L11) 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 1 and qb are the percent power in the top and bottom halves of the core respectively, and q 1 + qb is total core power in percent of RTP, such that: 2.9.1 For% -qb within -12, +6 percent, f(L11) = 0. 2.9.2 For each percent that the magnitude of q 1-qb exceeds +6 percent, the L1 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 q 1-qb exceeds -12 percent, the L1T 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 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 2.10 Overpower Setpoint (TS 3.3.1, Table 3.3.1-1 note 2) Overpower setpoint parameter values (for 1800 MWt core power): = indicated RTP, oF T = indicated RCS average temperature, °F T' ::s;; 576.0°F ::s;; 1.098 (NTSP) 1 ::s;; 1.111 (AVf Ks z 0.0 for increasing T Ks = 0.0 for decreasing T K6 z 0.00123 forT z T' K6 = 0.0 forT< T' 'ts z 0 sec 't3 = 4 sec '1:4 = 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 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. 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 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 37 FIGURE 1 TRM 2.1 U1 Revision 18 March 19, 2016 REACTOR CORE SAFETY LIMITS CURVE Unacceptable Operation 0.0 0.2 OA 0.6 0.8 1.0 Core Power (fraction of 1800 MWt) Page 8 of 18 1.2 1A POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 2 REQUIRED SHUTDOWN MARGIN .3 .. 5% 3.0% 2..5% > "' v "' l.O% ! = "' .2 = ?; L5% 0 -:::; .. c; 1.0% o.s%H= 0.0% 0 10 20 30 40 50 60 Core Burnup (%) Page 9 of 18 70 TRM 2.1 U1 Revision 18 March 19, 2016 80 90 100 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 ...-... c $: ro L-""0 ..c (/) c.. <I) ........ U) "--"" c 0 :p "(j) 0 0.... c ro co 0 L-........ c 0 () 240 225 210 195 180 165 150 135 120 105 90 75 60 45 30 15 0 FIGURE 3 CONTROL BANK INSERTION LIMITS 121% I / 168.50% I / / *l Bank B Insertion J / / / / 1§ / / / / 1 176l / / v 1 Bank C Insertion J // / / / / / / / v / v / / VI Bank D Insertion 1-r---v / v /v / v / /v / t28.50% 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 225 steps (Limits are always considered met when withdrawn position 225 steps). Page 10 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 4 TRM 2.1 U1 Revision 18 March 19, 2016 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) 1.2 1.1 1 co.o, 1.0) 1 1 (6.0, 1.0) 1 II (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 2 3 4 5 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 37 FIGURE 5 TRM 2.1 U1 Revision 18 March 19, 2016 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

WZ) Height (feet) 150 2000 10000 18000 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 1.0973 1.1009 1.1102 1.1250 1.8 1.0974 1.0997 1.1090 1.1220 2.0 1.0972 1.0982 1.1074 1.1182 2.2 1.0968 1.0967 1.1053 1.1139 2.4 1.0962 1.0956 1.1028 1.1090 2.6 1.0953 1.0949 1.1000 1.1036 2.8 1.0943 1.0940 1.0968 1.0980 3.0 1.0930 1.0928 1.0932 1.0917 3.2 1.0915 1.0913 1.0897 1.0866 3.4 1.0900 1.0898 1.0871 1.0838 3.6 1.0892 1.0890 1.0848 1.0820 3.8 1.0890 1.0887 1.0828 1.0821 4.0 1.0887 1.0884 1.0821 1.0826 4.2 1.0882 1.0878 1.0820 1.0826 4.4 1.0875 1.0870 1.0824 1.0826 4.6 1.0866 1.0860 1.0828 1.0824 4.8 1.0856 1.0846 1.0829 1.0819 5.0 1.0843 1.0832 1.0829 1.0815 5.2 1.0829 1.0815 1.0826 1.0811 5.4 1.0811 1.0796 1.0821 1.0805 5.6 1.0791 1.0775 1.0813 1.0795 5.8 1.0768 1.0752 1.0801 1.0782 6.0 1.0742 1.0726 1.0785 1.0766 Page 12 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 5 (can't) TRM 2.1 U1 Revision 18 March 19, 2016 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

WZ) Height (feet) 150 2000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0714 1.0695 1.0765 1.0745 6.4 1.0684 1.0663 1.0741 1.0722 6.6 1.0654 1.0637 1.0712 1.0715 6.8 1.0627 1.0613 1.0684 1.0738 7.0 1.0604 1.0593 1.0702 1.0777 7.2 1.0580 1.0575 1.0752 1.0810 7.4 1.0564 1.0566 1.0790 1.0840 7.6 1.0590 1.0602 1.0826 1.0866 7.8 1.0642 1.0658 1.0858 1.0888 8.0 1.0701 1.0717 1.0887 1.0907 8.2 1.0759 1.0775 1.0914 1.0921 8.4 1.0816 1.0831 1.0938 1.0932 8.6 1.0871 1.0886 1.0957 1.0939 8.8 1.0924 1.0938 1.0973 1.0943 9.0 1.0974 1.0988 1.0985 1.0945 9.2 1.1022 1.1034 1.0993 1.0947 9.4 1.1067 1.1078 1.1000 1.0949 9.6 1.1117 1.1125 1.1006 1.0956 9.8 1.1164 1.1171 1.1013 1.0963 10.0 1.1208 1.1214 1.1018 1.0966 10.2 1.1249 1.1253 1.1023 1.0969 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 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 5A TRM 2.1 U1 Revision 18 March 19, 2016 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 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 1.0000 1.6 1.1768 1.8 1.1730 2.0 1.1688 2.2 1.1641 2.4 1.1593 2.6 1.1543 2.8 1.1493 3.0 1.1439 3.2 1.1382 3.4 1.1325 3.6 1.1283 3.8 1.1245 4.0 1.1204 4.2 1.1159 4.4 1.1113 4.6 1.1065 4.8 1.1017 5.0 1.0966 5.2 1.0914 5.4 1.0855 5.6 1.0794 5.8 1.0730 6.0 1.0663 Page 14 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE SA (con't) BOC Part-Power Summary of W(Z) as a Function of Core Height (0-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 1.0594 6.4 1.0522 6.6 1.0450 6.8 1.0382 7.0 1.0321 7.2 1.0259 7.4 1.0203 7.6 1.0194 7.8 1.0203 8.0 1.0217 8.2 1.0231 8.4 1.0248 8.6 1.0264 8.8 1.0280 9.0 1.0291 9.2 1.0302 9.4 1.0314 9.6 1.0335 9.8 1.0357 10.0 1.0381 10.2 1.0406 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 15 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 6 TRM 2.1 U1 Revision 18 March 19, 2016 FLUX DIFFERENCE OPERATING ENVELOPE Pcw*e r Tech Spec 95 90 -40 NOTES: U!'.JACCEPTA8 LE CJPERATIO

[\j 20 { ! t .... "!' \ Level Envalcpe '11.0

1S.C

- 2&3J: 31.[} 11.0 1*:.Di 21.1} 2n.n 31.0 ! ; Ll-'----'---.

\\ Ut\i.A.CC:EPTABLE OPERATION 0 AGGEPTAJ3LE OPERATIO!'>l 0 10 Axial Flux Difference

\ \ \ \ \ \ 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 :2:15% RTP. Page 16 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 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.VŽ System," Revision 0, Mar 1997. Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.VŽ 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 (FQ(Z)) 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-1 0054-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 37 COLR Parameter Section 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN ,.,H) 2.8 Axial Flux Difference (AFD) 2.9 Overtemperature

,1 T Setpoint 2.10 Overpower

,1 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 18 March 19, 2016 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

,1 T and Thermal Overtemperature

,1 T Trip Functions," September 1986. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower

,1 T and Thermal Overtemperature

,1 T Trip Functions," September 1986. WCAP-11397-P-A, "Revised Thermal Design Procedure," April1989, 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 March 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 1 Docket No. 50-266 Renewed License No. DPR-24 Core Operating Limits Report (COLR) Unit 1 Cycle 37 (U1C37) In accordance with the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 1, Cycle 37. NRC 2016-0011 TS 5.6.4 The Enclosure to this letter contains the PBNP U1C37 COLR that was issued on March 19, 2016. This letter contains no new regulatory commitments and no revisions to existing commitments.

Sincerely, NextEra Energy Point Beach, LLC Bryan Woyak Licensing Manager Enclosure 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, Wl54241 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 (U1C37) ' ,*, 'i 18 pages follow TRM 2.1 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 REVISION 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 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 5A Figure 6 Table 1 PBNP Description TS 2.1.1 Reactor Core Safety Limits 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 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 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 llH) Axial Flux Difference (AFD) Overtemperature L1 T Setpoint Overpower L1 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 BOC 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 37 2.0 OPERATING LIMITS TRM 2.1 U1 Revision 18 March 19, 2016 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 (see Figure 2). Applicability:

MODES 1, 2, and 3 2.2.2 SDM shall be :::::1%

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 kett :::::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 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 2.5 Control Bank Insertion Limits (TS 3.1.6) TRM 2.1 U1 Revision 18 March 19, 2016 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: F 0 (Z) CF 0

K(Z) I P F 0 (Z) CF 0

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

F 0 (Z) is both:

Steady State

Transient CF 0 = 2.60 F 0 c(Z) = Fo(Z)

1.08 F 0 w(Z) = F 0 c(Z)

W(Z) I P for P>0.5 F 0 w(Z) = F 0 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 F 0 penalty factors are applicable to Cycle 37. Cycle Burnup Fw 0 (Z) Penalty (MWD/MTU)

Factors BOL 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 37 TRM 2.1 U1 Revision 18 March 19, 2016 2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN AH) (TS 3.2.2) The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: 2. 7.1 FN 8H :::;1.68 X [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 RTP Page 5 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 TRM 2.1 U1 Revision 18 March 19, 2016 2.9 Overtemperature L1T Setpoint CTS 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 K2 ;;::: 0.016 K3 ;;::: 0.000811 'L1 = 40 sec 'L2 = 8 sec 'L3 = 4 sec 'L4 = 2 sec f(L11) 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 1 and qb are the percent power in the top and bottom halves of the core respectively, and q 1 + qb is total core power in percent of RTP, such that: 2.9.1 For% -qb within -12, +6 percent, f(L11) = 0. 2.9.2 For each percent that the magnitude of q 1-qb exceeds +6 percent, the L1 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 q 1-qb exceeds -12 percent, the L1T 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 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 2.10 Overpower Setpoint (TS 3.3.1, Table 3.3.1-1 note 2) Overpower setpoint parameter values (for 1800 MWt core power): = indicated RTP, oF T = indicated RCS average temperature, °F T' ::s;; 576.0°F ::s;; 1.098 (NTSP) 1 ::s;; 1.111 (AVf Ks z 0.0 for increasing T Ks = 0.0 for decreasing T K6 z 0.00123 forT z T' K6 = 0.0 forT< T' 'ts z 0 sec 't3 = 4 sec '1:4 = 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 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. 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 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 37 FIGURE 1 TRM 2.1 U1 Revision 18 March 19, 2016 REACTOR CORE SAFETY LIMITS CURVE Unacceptable Operation 0.0 0.2 OA 0.6 0.8 1.0 Core Power (fraction of 1800 MWt) Page 8 of 18 1.2 1A POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 2 REQUIRED SHUTDOWN MARGIN .3 .. 5% 3.0% 2..5% > "' v "' l.O% ! = "' .2 = ?; L5% 0 -:::; .. c; 1.0% o.s%H= 0.0% 0 10 20 30 40 50 60 Core Burnup (%) Page 9 of 18 70 TRM 2.1 U1 Revision 18 March 19, 2016 80 90 100 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 ...-... c $: ro L-""0 ..c (/) c.. <I) ........ U) "--"" c 0 :p "(j) 0 0.... c ro co 0 L-........ c 0 () 240 225 210 195 180 165 150 135 120 105 90 75 60 45 30 15 0 FIGURE 3 CONTROL BANK INSERTION LIMITS 121% I / 168.50% I / / *l Bank B Insertion J / / / / 1§ / / / / 1 176l / / v 1 Bank C Insertion J // / / / / / / / v / v / / VI Bank D Insertion 1-r---v / v /v / v / /v / t28.50% 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 225 steps (Limits are always considered met when withdrawn position 225 steps). Page 10 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 4 TRM 2.1 U1 Revision 18 March 19, 2016 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) 1.2 1.1 1 co.o, 1.0) 1 1 (6.0, 1.0) 1 II (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 2 3 4 5 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 37 FIGURE 5 TRM 2.1 U1 Revision 18 March 19, 2016 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

WZ) Height (feet) 150 2000 10000 18000 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 1.0973 1.1009 1.1102 1.1250 1.8 1.0974 1.0997 1.1090 1.1220 2.0 1.0972 1.0982 1.1074 1.1182 2.2 1.0968 1.0967 1.1053 1.1139 2.4 1.0962 1.0956 1.1028 1.1090 2.6 1.0953 1.0949 1.1000 1.1036 2.8 1.0943 1.0940 1.0968 1.0980 3.0 1.0930 1.0928 1.0932 1.0917 3.2 1.0915 1.0913 1.0897 1.0866 3.4 1.0900 1.0898 1.0871 1.0838 3.6 1.0892 1.0890 1.0848 1.0820 3.8 1.0890 1.0887 1.0828 1.0821 4.0 1.0887 1.0884 1.0821 1.0826 4.2 1.0882 1.0878 1.0820 1.0826 4.4 1.0875 1.0870 1.0824 1.0826 4.6 1.0866 1.0860 1.0828 1.0824 4.8 1.0856 1.0846 1.0829 1.0819 5.0 1.0843 1.0832 1.0829 1.0815 5.2 1.0829 1.0815 1.0826 1.0811 5.4 1.0811 1.0796 1.0821 1.0805 5.6 1.0791 1.0775 1.0813 1.0795 5.8 1.0768 1.0752 1.0801 1.0782 6.0 1.0742 1.0726 1.0785 1.0766 Page 12 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 5 (can't) TRM 2.1 U1 Revision 18 March 19, 2016 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)

WZ) Height (feet) 150 2000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0714 1.0695 1.0765 1.0745 6.4 1.0684 1.0663 1.0741 1.0722 6.6 1.0654 1.0637 1.0712 1.0715 6.8 1.0627 1.0613 1.0684 1.0738 7.0 1.0604 1.0593 1.0702 1.0777 7.2 1.0580 1.0575 1.0752 1.0810 7.4 1.0564 1.0566 1.0790 1.0840 7.6 1.0590 1.0602 1.0826 1.0866 7.8 1.0642 1.0658 1.0858 1.0888 8.0 1.0701 1.0717 1.0887 1.0907 8.2 1.0759 1.0775 1.0914 1.0921 8.4 1.0816 1.0831 1.0938 1.0932 8.6 1.0871 1.0886 1.0957 1.0939 8.8 1.0924 1.0938 1.0973 1.0943 9.0 1.0974 1.0988 1.0985 1.0945 9.2 1.1022 1.1034 1.0993 1.0947 9.4 1.1067 1.1078 1.1000 1.0949 9.6 1.1117 1.1125 1.1006 1.0956 9.8 1.1164 1.1171 1.1013 1.0963 10.0 1.1208 1.1214 1.1018 1.0966 10.2 1.1249 1.1253 1.1023 1.0969 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 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 5A TRM 2.1 U1 Revision 18 March 19, 2016 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 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 1.0000 1.6 1.1768 1.8 1.1730 2.0 1.1688 2.2 1.1641 2.4 1.1593 2.6 1.1543 2.8 1.1493 3.0 1.1439 3.2 1.1382 3.4 1.1325 3.6 1.1283 3.8 1.1245 4.0 1.1204 4.2 1.1159 4.4 1.1113 4.6 1.1065 4.8 1.1017 5.0 1.0966 5.2 1.0914 5.4 1.0855 5.6 1.0794 5.8 1.0730 6.0 1.0663 Page 14 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE SA (con't) BOC Part-Power Summary of W(Z) as a Function of Core Height (0-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 1.0594 6.4 1.0522 6.6 1.0450 6.8 1.0382 7.0 1.0321 7.2 1.0259 7.4 1.0203 7.6 1.0194 7.8 1.0203 8.0 1.0217 8.2 1.0231 8.4 1.0248 8.6 1.0264 8.8 1.0280 9.0 1.0291 9.2 1.0302 9.4 1.0314 9.6 1.0335 9.8 1.0357 10.0 1.0381 10.2 1.0406 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 15 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 FIGURE 6 TRM 2.1 U1 Revision 18 March 19, 2016 FLUX DIFFERENCE OPERATING ENVELOPE Pcw*e r Tech Spec 95 90 -40 NOTES: U!'.JACCEPTA8 LE CJPERATIO

[\j 20 { ! t .... "!' \ Level Envalcpe '11.0

1S.C

- 2&3J: 31.[} 11.0 1*:.Di 21.1} 2n.n 31.0 ! ; Ll-'----'---.

\\ Ut\i.A.CC:EPTABLE OPERATION 0 AGGEPTAJ3LE OPERATIO!'>l 0 10 Axial Flux Difference

\ \ \ \ \ \ 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 :2:15% RTP. Page 16 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U1 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR) UNIT 1 CYCLE 37 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.VŽ System," Revision 0, Mar 1997. Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.VŽ 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 (FQ(Z)) 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-1 0054-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 37 COLR Parameter Section 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN ,.,H) 2.8 Axial Flux Difference (AFD) 2.9 Overtemperature

,1 T Setpoint 2.10 Overpower

,1 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 18 March 19, 2016 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

,1 T and Thermal Overtemperature

,1 T Trip Functions," September 1986. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower

,1 T and Thermal Overtemperature

,1 T Trip Functions," September 1986. WCAP-11397-P-A, "Revised Thermal Design Procedure," April1989, 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

NRC 2016-0011, Core Operating Limits Report (COLR) Cycle 37 (U1C37): Difference between revisions

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5.6.4 Physics

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2.4.2 Fully

2.6 Nuclear

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NRC 2016-0011, Core Operating Limits Report (COLR) Cycle 37 (U1C37): Difference between revisions

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5.6.4 Physics

2.4 Shutdown

2.4.2 Fully

2.6 Nuclear

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2.6 Nuclear

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