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#REDIRECT [[NRC 2014-0028, Core Operating Limits Reports (COLR) Unit 2 Cycle 34 (U2C34)]]
| number = ML14101A274
| issue date = 04/11/2014
| title = Core Operating Limits Reports (Colr) Unit 2 Cycle 34 (U2C34)
| author name = Millen M
| author affiliation = NextEra Energy Point Beach, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000301
| license number = DPR-027
| contact person =
| case reference number = NRC 2014-0028, TS 5.6.4
| document type = Fuel Cycle Reload Report, Letter
| page count = 20
}}
 
=Text=
{{#Wiki_filter:April 11, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 2 Docket No. 50-301 Renewed License No. DPR-27 Core Operating Limits Report (COLR) Unit 2 Cycle 34 (U2C34) NEXT era*** POINT BEACH NRC 2014-0028 TS 5.6.4 In accordance with the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.4, enclosed is revised TRM 2.1, COLR, Unit 2 Cycle 34. The enclosure to this letter contains the revised PBNP U2C34 COLR that was issued on March 26, 2014. This letter contains no new regulatory commitments and no revisions to existing commitments.
Very truly yours, NextEra Energy Point Beach, LLC Michael Millen 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, WI 54241 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 2 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 (U2C34) 18 pages follow TRM 2.1 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 REVISION 17 POINT B E ACH NUCL E AR PLAN T T E CHNICAL R E QUIR E M E NTS MANUAL COR E OPERATING LIMITS REPOR T (COLR) UNIT 2 CYCLE 34 1.0 CORE OPERATING LIMITS REPORT TRM 2.1 U2 Revision 17 March 26, 2014 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 Insert i on Limit 2.5 3.1.6 Control Bank Insertion Limits 2.6 3.2.1 Nuclear Heat Flux Hot Channel Factor (Fo(Z)) 2.7 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature
.0. T Setpoint 2.10 3.3.1 Overpower
.0. 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 BOC 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 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 2.0 OPERATING LIMITS TRM 2.1 U2 Revision 17 March 26, 2014 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% .l1k/k (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: ::>5 pcmrF for power levels ::>70% RTP ::>0 pcmrF 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 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 2.5 Control Bank Insertion Limits (TS 3.1.6) TRM 2.1 U2 Revision 17 March 26, 2014 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 ke 11 <::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) ::; CFQ
* K(Z) I P F 0 (Z)::; CFQ
* 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) = F 0 (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 5A The following FQ penalty factors are applicable to Cycle 34. Cycle Burnup F o(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 2 CYCLE 34 2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN 6 H) (TS 3.2.2) TRM 2.1 U2 Revision 17 March 26, 2014 The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit: 2.7.1 FN8H <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 +/-5%. The AFD Acceptability Operation Limits are provided in Figure 6. Applicability:
MODE 1 with THERMAL POWER >15% RTP 2.9 Setpoint (TS 3.3.1, Table 3.3.1-1 note 1) Overtemperature setpoint parameter values (for 1800 MWt core power): = indicated RTP, oF T = indicated RCS average temperature, oF T' ::;; 576.0&deg;F p = pressurizer pressure, psig P' ;;:::: 2235 psig K1 ::;; 1.175 (NTSP}1 K1 ::;; 1.188 (AV)2 K2 ;;:::: 0.016 K3 ;;:::: 0.000811 11 = 40 sec 12 = 8 sec 13 = 4 sec 14 = 2 sec is an event 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: 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 34 2.9.1 For q 1-qb within -12, +6 percent,
= 0. TRM 2.1 U2 Revision 17 March 26, 2014 2.9.2 For each percent that the magnitude of q 1-qb exceeds +6 percent, the 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 trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power. Applicability
: MODES 1 and 2 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, oF T' ::; 576.0&deg;F K4 ::; 1.098 (NTSP)1 ::; 1.111 (AV)2 Ks = 0.0 for increasing T Ks = 0.0 for decreasing T K6 0.00123 T' K6 = 0.0 forT< T' 'l:s = 0 sec 1:3 = 4 sec '1:4 = 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 34 TRM 2.1 U2 Revision 17 March 26, 2014 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.11.1 Tavg shall be S57rF. 2.11.2 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. 2.11.3 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 Page 7 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE TRM 2.1 U2 Revision 17 March 26, 2014 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 2.5% ii *> . ., l 2.0% 1.5% l 1.0 90 0.5% 0.0 90 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 FIGURE 2 REQUIRED SHUTDOWN MARGIN I w w
* w ti
* I I
* I I I li * * * *
* I +/-tW * * * *
* 1---f---* I * *
* iij *
* I w w w w Q w -*
* Ill* *
* H-:--:-1m
* Q JUl w w w ---M -I I I --r-TRM 2.1 U2 Revision 17 March 26, 2014 Q Q ww l.O% -,----J+ I * $1
* M !lt ffl = 10 20 30 40 50 60 70 80 90 100
(%} Page 9 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 17 March 26, 2014 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 .-c :s: co ..... ""0 ...... s: en 0.. Q) ...... en ..........
c 0 :0::0 "(j) 0 a.. c co en e ...... 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 / 1 68.50% I v 'I Bank B Insertion I / v L / 1ill / v / L [f176l / / v 1 Bank C Insertion 1 v / v / v / / v / v v L V I Bank D Insertion 1-v / v v / v 1/ / v 1 28.50% 1/ v ....r 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 34 FIGURE 4 TRM 2.1 U2 Revision 17 March 26 , 2014 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z)) 1.2 1.1 1 (O.o, 1.0) 1 1(6.0, 1.0)1 1 (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 HE.IGHf (FI) Page 11 of 18 12 POIN T B E ACH NUCL E AR PLAN T T E CHNICAL R E QUIR E MENTS MANUAL COR E OP E RATING LIMITS R E PORT (COLR) UNIT 2 CYCLE 34 FIGURE 5 TRM 2.1 U 2 Revision 17 March 26, 2014 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Height W(Z) (feet) 150 2000 8000 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 1.0971 1.0967 1.1065 1.1231 1.8 1.0972 1.0969 1.105 7 1.1202 2.0 1.0971 1.0968 1.1045 1.1166 2.2 1.0966 1.0964 1.1029 1.1124 2.4 1.0959 1.0958 1.1009 1.1077 2.6 1.0950 1.0949 1.0986 1.1025 2.8 1.0939 1.0938 1.0959 1.0971 3.0 1.0925 1.0924 1.0929 1.0909 3.2 1.0909 1.0907 1.0899 1.0868 3.4 1.0895 1.0894 1.0871 1.0841 3.6 1.0887 1.0883 1.0853 1.0825 3.8 1.0883 1.0877 1.0836 1.0821 4.0 1.0876 1.0872 1.0822 1.0821 4.2 1.0868 1.0864 1.0811 1.0827 4.4 1.0859 1.0853 1.0803 1.0835 4.6 1.0848 1.0841 1.0797 1.0840 4.8 1.0836 1.0829 1.0790 1.0843 5.0 1.0821 1.0816 1.0785 1.0843 5.2 1.0804 1.0799 1.0778 1.0840 5.4 1.0785 1.0 7 81 1.0769 1.0834 5.6 1.0764 1.0 7 59 1.0757 1.0824 5.8 1.0739 1.0736 1.0742 1.0810 6.0 1.0715 1.0708 1.0 7 23 1.0791 Page 12 of 18 POINT BEACH NUCL E AR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 FIGURE 5 (con't) TRM 2.1 U2 Revision 17 March 26, 2014 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Height W(Z) (feet) 150 2000 8000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0690 1.0678 1.0702 1.0767 6.4 1.0663 1.0644 1.0689 1.0740 6.6 1.0636 1.0620 1.0677 1.0737 6.8 1.0612 1.0602 1.0655 1.0773 7.0 1.0592 1.0590 1.0656 1.0803 7.2 1.0573 1.0577 1.0691 1.0831 7.4 1.0564 1.0572 1.0735 1.0854 7.6 1.0601 1.0624 1.0775 1.0874 7.8 1.0658 1.0685 1.0814 1.0891 8.0 1.0718 1.0742 1.0850 1.0903 8.2 1.0775 1.0798 1.0883 1.0913 8.4 1.0832 1.0853 1.0913 1.0919 8.6 1.0886 1.0905 1.0939 1.0923 8.8 1.0939 1.0955 1.0962 1.0923 9.0 1.0988 1.1002 1.0981 1.0923 9.2 1.1034 1.1045 1.0995 1.0923 9.4 1.1076 1.1084 1.1005 1.0926 9.6 1.1122 1.1127 1.1017 1.0927 9.8 1.1166 1.1168 1.1030 1.0932 10.0 1.1206 1.1206 1.1035 1.0943 10.2 1.1240 1.1238 1.1043 1.0956 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 B E ACH NUCL E AR PLANT T E CHNICAL R E QUIR E MENTS MANUAL COR E OPERATING LIMITS REPORT (COLR) UNIT 2 CYCL E 34 FIGURE 5A TRM 2.1 U2 Revision 17 March 26 , 2014 BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Height Part -Power W(Z) with Correction Factor (excluding power ratio) (feet) Hot Full Power 30% Power 50% Power 75% Power 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 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 1.0971 1.3805 1.2720 1.1734 1.8 1.0972 1.3658 1.2638 1.1699 2 1.0971 1.3477 1.2537 1.1655 2.2 1.0966 1.3276 1.2422 1.1602 2.4 1.0959 1.3088 1.2311 1.1552 2.6 1.0950 1.2913 1.2204 1.1502 2.8 1.0939 1.2 7 41 1.2096 1.1449 3 1.0925 1.2564 1.1982 1.1390 3.2 1.0909 1.2383 1.1867 1.1331 3.4 1.0895 1.2205 1.1759 1.1276 3.6 1.0887 1.2041 1.1657 1.1226 3.8 1.0883 1.1886 1.1559 1.1178 4 1.0876 1.1731 1.1457 1.1126 4.2 1.0868 1.15 7 6 1.1353 1.1073 4.4 1.0859 1.1422 1.1250 1.1019 4.6 1.0848 1.1268 1.1146 1.0963 4.8 1.0836 1.1116 1.1044 1.0906 5 1.0821 1.0966 1.0941 1.0846 5.2 1.0804 1.0817 1.0835 1.0786 5.4 1.0 7 85 1.0668 1.0727 1.0725 5.6 1.0764 1.0530 1.0627 1.0665 5.8 1.0739 1.0390 1.0523 1.0601 6 1.0715 1.0251 1.0417 1.0536 Page 14 of 18 POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 FIGURE 5A (can't) TRM 2.1 U2 Revision 17 March 26, 2014 BOC Part-Power Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
Height Part -Power W(Z) with Correction Factor (excluding power ratio) (feet) Hot Full Power 30% Power 50% Power 75% Power 6.2 1.0690 1.0114 1.0310 1.0468 6.4 1.0663 1.0000 1.0204 1.0398 6.6 1.0636 1.0000 1.0097 1.0330 6.8 1.0612 1.0000 1.0000 1.0267 7 1.0592 1.0000 1.0000 1.0206 7.2 1.0573 1.0000 1.0000 1.0147 7.4 1.0564 1.0000 1.0000 1.0099 7.6 1.0601 1.0000 1.0000 1.0098 7.8 1.0658 1.0000 1.0000 1.0119 8 1.0718 1.0000 1.0000 1.0146 8.2 1.0775 1.0000 1.0000 1.0171 8.4 1.0832 1.0000 1.0000 1.0196 8.6 1.0886 1.0000 1.0000 1.0220 8.8 1.0939 1.0000 1.0000 1.0245 9 1.0988 1.0000 1.0000 1.0273 9.2 1.1034 1.0000 1.0000 1.0306 9.4 1.1076 1.0000 1.0000 1.0347 9.6 1.1122 1.0000 1.0000 1.0402 9.8 1.1166 1.0000 1.0000 1.0461 10 1.1206 1.0000 1.0000 1.0518 10.2 1.1240 1.0000 1.0000 1.0617 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 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 1.0000 1.0000 1.0000 1.0000 Page15of18 POINT B E ACH NUCL E AR PLANT TECHNICAL REQUIREMENTS MANUAL CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 FIGURE 6 TRM 2.1 U2 Revision 17 March 26, 2014 FLUX DIFFERENCE OPERATING ENVELOPE -.. .... (1) 0 0.. -o tl l ....... I;Q a: NOTE: 1 00 95 90 85 75 70 -40 Llf\JACCEPTAB LE OPERAT I ON 2 0 l ' I . ACC EP TAB LE OPERAT IO N I. I , I P o*we r L e v e l 0/ '" &0 80 70 60 50 l : r I -10 0 1 0 Axia l Flux Difference T ech Spec Envel o p e %] *11.0 11.0 -Hl.O 1 6.0 -21.0 21.0 -2 5.0 26.0 -3 1.0 3'1.0 U h!A CCE PTA.BL E OPERATIO 1'**1 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. Page16of18 I I I I I I I I POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 17 March 26, 2014 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section All Reactor Thermal Output Caldon, Inc., Engineering Report-SOP, "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM"&#x17d; System," Revision 0, Mar 1997. Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM"&#x17d; 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 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-1 0054-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 17 of 18 I I POINT BEACH NUCLEAR PLANT TECHNICAL REQUIREMENTS MANUAL TRM 2.1 U2 Revision 17 March 26, 2014 CORE OPERATING LIMITS REPORT (COLR) UNIT 2 CYCLE 34 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 ,., 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 Ll T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower Ll T and Thermal Overtemperature Ll T Trip Functions," September 1986 2.10 Overpower Ll T Set point WCAP-8745-P-A, "Design Bases for the Thermal Overpower Ll T and Thermal Overtemperature Ll 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}}

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