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

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{{#Wiki_filter: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.
{{#Wiki_filter:March 29, 2016                                                             NRC 2016-0011 TS 5.6.4 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)
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.
In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
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:
Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 1, Cycle 37.
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:
The Enclosure to this letter contains the PBNP U1C37 COLR that was issued on March 19, 2016.
MODES 1, 2, and 3 2.2.2 SDM shall be :::::1%
This letter contains no new regulatory commitments and no revisions to existing commitments.
Applicability:
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
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:
. NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, Wl54241
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.
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 CORE OPERATING LIMITS REPORT (COLR)
2.4.2 Fully withdrawn is defined as::::: 225 steps. Applicability:
UNIT 1 CYCLE 37 (U1C37)
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:
                            ' ,*, 'i 18 pages follow
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
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
* 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.
UNIT 1 CYCLE 37 REVISION 18
F 0 (Z) is both:
 
* Steady State
POINT BEACH NUCLEAR PLANT                                       TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                    Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
* Transient CF 0 = 2.60 F 0 c(Z) = Fo(Z)
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.
* 1.08 F 0 w(Z) = F 0 c(Z)
A cross-reference between the COLR sections and the PBNP Technical Specifications affected by this report is given below:
* W(Z) I P for P>0.5 F 0 w(Z) = F 0 c(Z)
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))
* 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)
2.7            3.2.2    Nuclear Enthalpy Rise Hot Channel Factor (FNllH) 2.8            3.2.3     Axial Flux Difference (AFD) 2.9            3.3.1    Overtemperature L1T Setpoint 2.10            3.3.1     Overpower L1T 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))
Factors BOL to EOL 1.02 Applicability:
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
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)]
 
POINT BEACH NUCLEAR PLANT                                              TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                          Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 2.0  OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4.
2.1      Reactor Core Safety Limits (TS 2.1.1)
The combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 1.
Applicability: MODES 1 and 2 2.2     Shutdown Margin (TS 3.1.1 and referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.2.1       SDM shall be  ~.0% ~klk  (see Figure 2).
Applicability: MODES 1, 2, and 3 2.2.2      SDM shall be :::::1% ~klk.
Applicability: MODES 4 and 5 2.3      Moderator Temperature Coefficient (TS 3.1.3) 2.3.1      The upper MTC limits shall be maintained within the limits.
2.3.2       The maximum upper MTC limits shall be:
                          ~5 pcm/°F for power levels ~70% RTP
                          ~0 pcm/°F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with 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                                            TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                        Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 2.5  Control Bank Insertion Limits (TS 3.1.6)
NOTE:        This limit is not applicable while performing SR 3.1.4.2.
The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3.
Applicability: MODE 1 and MODE 2 with keff ::::::1.0 2.6  Nuclear Heat Flux Hot Channel Factor (F0 (Z)) (TS 3.2.1)
The Heat Flux Hot Channel Factor shall be within the following limits:
F0 (Z) ~ CF0
* K(Z) I P          for P > 0.5 F0 (Z) ~ CF0
* K(Z) I 0.5        for P ~ 0.5 Where P is the fraction of Rated Power at which the core is operating.
F0 (Z) is both:
* Steady State        F0 c(Z) = Fo(Z)
* 1.08
* Transient            F0 w(Z) = F0 c(Z)
* W(Z) I P for P>0.5 F0 w(Z) =F0 c(Z)
* W(Z) I 0.5 for P_::: 0.5 CF 0 =2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and SA The following F0 penalty factors are applicable to Cycle 37.
Cycle Burnup              Fw0 (Z) Penalty (MWD/MTU)                   Factors BOL to EOL                      1.02 Applicability: MODE 1 Page 4 of 18
 
POINT BEACH NUCLEAR PLANT                                        TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                    Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37
: 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.
where: Pis the fraction of Rated Power at which the core is operating.
Applicability:
Applicability: MODE 1 2.8   Axial Flux Difference (AFD) (TS 3.2.3)
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:
The AFD target band is +/-5%.
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:
The AFD Acceptability Operation Limits are provided in Figure 6.
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, &deg;F T' ::s;; 576.0&deg;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:
Applicability: MODE 1 with THERMAL POWER         ~15% RTP Page 5 of 18
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.
POINT BEACH NUCLEAR PLANT                                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
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
UNIT 1 CYCLE 37 2.9     Overtemperature L1T Setpoint CTS 3.3.1. Table 3.3.1-1 note 1)
::::186,000 gpm. Applicability:
Overtemperature L1 T setpoint parameter values (for 1800 MWt core power):
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
L1To     =     indicated L1T at 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
::::2350 ppm. Applicability:
                'L1     =     40 sec
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&sect; / / / / 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)
                'L2     =     8 sec
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)
                'L3     =     4 sec
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::::;;
                '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 q1 and qb are the percent power in the top and bottom halves of the core respectively, and q1 + qb is total core power in percent of RTP, such that:
205 steps) (Top 15% and Bottom 12% Excluded)
2.9.1           For% - qb within -12, +6 percent, f(L11) =0.
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)
2.9.2           For each percent that the magnitude of q1 - qb exceeds +6 percent, the L1T trip setpoint shall be automatically reduced by an equivalent of 2.00 percent of Rated Power.
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
2.9.3           For each percent that the magnitude of q1 - qb exceeds -12 percent, the L1T trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.
[\j 20 { ! t .... "!' \ Level Envalcpe '11.0
Applicability: MODES 1 and 2 1
* 1S.C  
Nominal Setpoint Value 2
**2&3J: 31.[} 11.0 1*:.Di 21.1} 2n.n 31.0 ! ; Ll-'----'---.  
Allowable Value Page 6 of 18
\\ 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.V&#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.V&#x17d; System," Revision 0, May 2000. Fuel Assembly WCAP-12610-P-A, "VANTAGE+
POINT BEACH NUCLEAR PLANT                                               TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                          Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
Fuel Assembly Reference Core Report," April 1995. WCAP-12610-P-A  
UNIT 1 CYCLE 37 2.10   Overpower     ~T    Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)
& CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO&#x17d;," 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
Overpower     ~T    setpoint parameter values (for 1800 MWt core power):
,1 T Setpoint 2.10 Overpower
                ~To          =       indicated ~Tat RTP, oF T         =       indicated RCS average temperature, &deg;F T'         ::s;;   576.0&deg;F
,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  
                  ~          ::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       Pressurizer pressure shall be maintained ::::2205 psig during operation.
NOTE:         Pressurizer pressure limit does not apply during:
: 1)   THERMAL POWER ramp >5% RTP per minute; or
: 2)   THERMAL POWER step >10% RTP.
2.11.3      Reactor Coolant System raw measured Total Flow Rate shall be maintained
::::186,000 gpm.
Applicability: MODE 1 2.12   Refueling Boron Concentration (TS 3. 9. 1)
Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ::::2350 ppm.
Applicability: MODE 6 1
Nominal Setpoint Value 2
Allowable Value Page 7 of 18
 
POINT BEACH NUCLEAR PLANT                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680r------.-------r------.-------,------,------,-----~
Unacceptable Operation 540+-----~-------+------4-------~-----+------~----~
0.0    0.2    OA      0.6        0.8      1.0         1.2    1A Core Power (fraction of 1800 MWt)
Page 8 of 18
 
POINT BEACH NUCLEAR PLANT                                          TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                      Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 2 REQUIRED SHUTDOWN MARGIN
      .3 ..5%
3.0%
2..5%
~
>
"'v
!"'
l.O%
*~=
.2"'
  =
.?;
0
-:::;
  ~
L5%
c; 1.0%
o.s%H=
0.0%
0 10    20      30      40          50        60 70    80        90 100 Core Burnup (%)
Page 9 of 18
 
POINT BEACH NUCLEAR PLANT                                                  TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                              Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 3 CONTROL BANK INSERTION LIMITS 240 225                        121% I                              / 168.50% I
                                    /                                       /
        ...-... 210              *l Bank B Insertion J                  /
c                    /
          $:    195        /                                        /
ro              /                                                                         1&sect; L-
        ""0      180  /                                         /                                     /
        ..c 1176l                                  /                                       v
        ~        165                                                                              /
1Bank C Insertion J               /
(/)
150
                                                        //                                   /
c..                                          /
          <I)
        ........
135                                /                                     /
U)
        "--""
                                              /
                                                  /
v
:p c
0
        "(j) 120 105                      /                                    /
v 0                      /                                         VI   Bank D Insertion 1-0....
        ~
c 90 75 v                                      /
v                            r---
ro            /v                                         v co      60 /                                             /
0                                                  /v 45
                    ~~
L-
        ........
c
()
0      30                                      /
15                  t28.50%       v/
I       .A' 0
0  5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power Level (% of Rated Power)
NOTE:       The Figure is applicable for any fully withdrawn position of~ 225 steps (Limits are always considered met when withdrawn position is~ 225 steps).
Page 10 of 18
 
POINT BEACH NUCLEAR PLANT                                       TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                   Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
1.2 1.1 1co.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       12 CORE HEIGHT (FI)
Page 11 of 18
 
POINT BEACH NUCLEAR PLANT                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 5 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                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 5 (can't)
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                                       TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                   Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 5A 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                                   TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                              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                                               TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                           Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE 1oo~r----------r-IT!=--=;:=;:::::::::===;::::::::=~~==::;--,
Pcw*e r            Tech Spec Level             Envalcpe
                                                                            =~t                  ~~~
                                                                                          '11.0       11.0 95
* 1S.C     1:.Di
{                            ~2"1.1}    21.1}
                                                            !                            **2&3J:     2n.n t                              31.[}     31.0 90                                        ...."!'
                                                            !
                                                            ;
                                                                        \
U!'.JACCEPTA8 LE                                    \\       Ut\i.A.CC:EPTABLE CJPERATIO [\j                                                OPERATION Ll-'----'---.
AGGEPTAJ3LE OPERATIO!'>l
                                                                              \
                                                                                  \
                                                                                    \\
                                                                                      \
                                                                                        \
                -40        -30      -20          0          0      10          20             30       40 Axial Flux Difference NOTES:
: 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                                     TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                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.V' System," Revision 0, Mar 1997.
Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.V' 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 ZIRLO'," 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                                     TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 COLR Parameter                     NRC Approved Methodology Section 2.7   Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor (FN,.,H)                   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.
2.8    Axial Flux Difference (AFD)        WCAP-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," September 1974.
NS-TMA-2198, Westinghouse to NRC Letter


==Attachment:==
==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  
  "Operation and Safety Analysis Aspects of an Improved Load Follow Package,"
,1 T and Thermal Overtemperature  
January 31, 1980.
,1 T Trip Functions," September 1986. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower  
NS-CE-687, Westinghouse to NRC Letter, "Power Distribution Control Analysis," July 16, 1975.
,1 T and Thermal Overtemperature  
2.9    Overtemperature ,1T Setpoint      WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"
,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.
September 1986.
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.
2.10    Overpower ,1T Setpoint            WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"
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:
September 1986.
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:
2.11    RCS Pressure, Temperature, and    WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate      Procedure," April1989, for those events Boiling (DNB) Limits              analyzed using RTDP.
MODES 1, 2, and 3 2.2.2 SDM shall be :::::1%
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.
Applicability:
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP.
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/&deg;F for power levels RTP pcm/&deg;F for power levels > 70% RTP Applicability:
2.12    Refueling Boron Concentration    WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
MODE 1 and MODE 2 with kett :::::1.0.
Page 18 of 18
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:
March 29, 2016                                                             NRC 2016-0011 TS 5.6.4 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)
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:
In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
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
Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 1, Cycle 37.
* K(Z) I P F 0 (Z) CF 0
The Enclosure to this letter contains the PBNP U1C37 COLR that was issued on March 19, 2016.
* 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.
This letter contains no new regulatory commitments and no revisions to existing commitments.
F 0 (Z) is both:
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
* Steady State
. NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, Wl54241
* Transient CF 0 = 2.60 F 0 c(Z) = Fo(Z)
 
* 1.08 F 0 w(Z) = F 0 c(Z)
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 CORE OPERATING LIMITS REPORT (COLR)
* W(Z) I P for P>0.5 F 0 w(Z) = F 0 c(Z)
UNIT 1 CYCLE 37 (U1C37)
* 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)
                            ' ,*, 'i 18 pages follow
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)]
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 REVISION 18
 
POINT BEACH NUCLEAR PLANT                                       TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                    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           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 (FNllH) 2.8            3.2.3     Axial Flux Difference (AFD) 2.9            3.3.1     Overtemperature L1T Setpoint 2.10            3.3.1     Overpower L1T Setpoint 2.11            3.4.1     RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12            3.9.1     Refueling Boron Concentration Figure 1        2.1.1     Reactor Core Safety Limits Curve Figure 2        3.1.1     Required Shutdown Margin Figure 3        3.1.6     Control Bank Insertion Limits Figure 4        3.2.1     Hot Channel Factor Normalized Operating Envelope (K(Z))
Figure 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                                              TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                          Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 2.0  OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4.
2.1      Reactor Core Safety Limits (TS 2.1.1)
The combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 1.
Applicability: MODES 1 and 2 2.2      Shutdown Margin (TS 3.1.1 and referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.2.1      SDM shall be  ~.0% ~klk  (see Figure 2).
Applicability: MODES 1, 2, and 3 2.2.2       SDM shall be :::::1% ~klk.
Applicability: MODES 4 and 5 2.3      Moderator Temperature Coefficient (TS 3.1.3) 2.3.1       The upper MTC limits shall be maintained within the limits.
2.3.2      The maximum upper MTC limits shall be:
                          ~5 pcm/&deg;F for power levels ~70% RTP
                          ~0 pcm/&deg;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                                            TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                        Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 2.5  Control Bank Insertion Limits (TS 3.1.6)
NOTE:        This limit is not applicable while performing SR 3.1.4.2.
The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3.
Applicability: MODE 1 and MODE 2 with keff ::::::1.0 2.6  Nuclear Heat Flux Hot Channel Factor (F0 (Z)) (TS 3.2.1)
The Heat Flux Hot Channel Factor shall be within the following limits:
F0 (Z) ~ CF0
* K(Z) I P          for P > 0.5 F0 (Z) ~ CF0
* K(Z) I 0.5        for P ~ 0.5 Where P is the fraction of Rated Power at which the core is operating.
F0 (Z) is both:
* Steady State        F0 c(Z) = Fo(Z)
* 1.08
* Transient            F0 w(Z) = F0 c(Z)
* W(Z) I P for P>0.5 F0 w(Z) =F0 c(Z)
* W(Z) I 0.5 for P_::: 0.5 CF 0 =2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and SA The following F0 penalty factors are applicable to Cycle 37.
Cycle Burnup              Fw0 (Z) Penalty (MWD/MTU)                   Factors BOL to EOL                      1.02 Applicability: MODE 1 Page 4 of 18
 
POINT BEACH NUCLEAR PLANT                                        TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                    Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37
: 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.
where: Pis the fraction of Rated Power at which the core is operating.
Applicability:
Applicability: MODE 1 2.8   Axial Flux Difference (AFD) (TS 3.2.3)
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:
The AFD target band is +/-5%.
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&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 '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:
The AFD Acceptability Operation Limits are provided in Figure 6.
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, &deg;F T' ::s;; 576.0&deg;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:
Applicability: MODE 1 with THERMAL POWER         ~15% RTP Page 5 of 18
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.
POINT BEACH NUCLEAR PLANT                                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
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
UNIT 1 CYCLE 37 2.9     Overtemperature L1T Setpoint CTS 3.3.1. Table 3.3.1-1 note 1)
::::186,000 gpm. Applicability:
Overtemperature L1 T setpoint parameter values (for 1800 MWt core power):
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
L1To     =     indicated L1T at 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
::::2350 ppm. Applicability:
                'L1     =     40 sec
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&sect; / / / / 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)
                'L2     =     8 sec
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)
                'L3     =     4 sec
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::::;;
                '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 q1 and qb are the percent power in the top and bottom halves of the core respectively, and q1 + qb is total core power in percent of RTP, such that:
205 steps) (Top 15% and Bottom 12% Excluded)
2.9.1           For% - qb within -12, +6 percent, f(L11) =0.
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)
2.9.2           For each percent that the magnitude of q1 - qb exceeds +6 percent, the L1T trip setpoint shall be automatically reduced by an equivalent of 2.00 percent of Rated Power.
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
2.9.3           For each percent that the magnitude of q1 - qb exceeds -12 percent, the L1T trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.
[\j 20 { ! t .... "!' \ Level Envalcpe '11.0
Applicability: MODES 1 and 2 1
* 1S.C  
Nominal Setpoint Value 2
**2&3J: 31.[} 11.0 1*:.Di 21.1} 2n.n 31.0 ! ; Ll-'----'---.  
Allowable Value Page 6 of 18
\\ 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.V&#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.V&#x17d; System," Revision 0, May 2000. Fuel Assembly WCAP-12610-P-A, "VANTAGE+
POINT BEACH NUCLEAR PLANT                                               TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                          Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
Fuel Assembly Reference Core Report," April 1995. WCAP-12610-P-A  
UNIT 1 CYCLE 37 2.10   Overpower     ~T    Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)
& CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO&#x17d;," 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
Overpower     ~T    setpoint parameter values (for 1800 MWt core power):
,1 T Setpoint 2.10 Overpower
                ~To          =       indicated ~Tat RTP, oF T         =       indicated RCS average temperature, &deg;F T'         ::s;;   576.0&deg;F
,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  
                  ~          ::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       Pressurizer pressure shall be maintained ::::2205 psig during operation.
NOTE:         Pressurizer pressure limit does not apply during:
: 1)   THERMAL POWER ramp >5% RTP per minute; or
: 2)   THERMAL POWER step >10% RTP.
2.11.3      Reactor Coolant System raw measured Total Flow Rate shall be maintained
::::186,000 gpm.
Applicability: MODE 1 2.12   Refueling Boron Concentration (TS 3. 9. 1)
Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ::::2350 ppm.
Applicability: MODE 6 1
Nominal Setpoint Value 2
Allowable Value Page 7 of 18
 
POINT BEACH NUCLEAR PLANT                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680r------.-------r------.-------,------,------,-----~
Unacceptable Operation 540+-----~-------+------4-------~-----+------~----~
0.0    0.2    OA      0.6        0.8      1.0         1.2    1A Core Power (fraction of 1800 MWt)
Page 8 of 18
 
POINT BEACH NUCLEAR PLANT                                          TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                      Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 2 REQUIRED SHUTDOWN MARGIN
      .3 ..5%
3.0%
2..5%
~
>
"'v
!"'
l.O%
*~=
.2"'
  =
.?;
0
-:::;
  ~
L5%
c; 1.0%
o.s%H=
0.0%
0 10    20      30      40          50        60 70    80        90 100 Core Burnup (%)
Page 9 of 18
 
POINT BEACH NUCLEAR PLANT                                                  TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                              Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 3 CONTROL BANK INSERTION LIMITS 240 225                        121% I                              / 168.50% I
                                    /                                       /
        ...-... 210              *l Bank B Insertion J                  /
c                    /
          $:    195        /                                        /
ro              /                                                                         1&sect; L-
        ""0      180  /                                         /                                     /
        ..c 1176l                                  /                                       v
        ~        165                                                                              /
1Bank C Insertion J               /
(/)
150
                                                        //                                   /
c..                                          /
          <I)
        ........
135                                /                                     /
U)
        "--""
                                              /
                                                  /
v
:p c
0
        "(j) 120 105                      /                                    /
v 0                      /                                         VI   Bank D Insertion 1-0....
        ~
c 90 75 v                                      /
v                            r---
ro            /v                                         v co      60 /                                             /
0                                                  /v 45
                    ~~
L-
        ........
c
()
0      30                                      /
15                  t28.50%       v/
I       .A' 0
0  5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power Level (% of Rated Power)
NOTE:       The Figure is applicable for any fully withdrawn position of~ 225 steps (Limits are always considered met when withdrawn position is~ 225 steps).
Page 10 of 18
 
POINT BEACH NUCLEAR PLANT                                       TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                   Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
1.2 1.1 1co.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       12 CORE HEIGHT (FI)
Page 11 of 18
 
POINT BEACH NUCLEAR PLANT                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 5 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                                 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                             Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 5 (can't)
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                                       TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                   Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 5A 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                                   TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                              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                                               TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                           Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE 1oo~r----------r-IT!=--=;:=;:::::::::===;::::::::=~~==::;--,
Pcw*e r            Tech Spec Level             Envalcpe
                                                                            =~t                  ~~~
                                                                                          '11.0       11.0 95
* 1S.C     1:.Di
{                            ~2"1.1}    21.1}
                                                            !                            **2&3J:     2n.n t                              31.[}     31.0 90                                        ...."!'
                                                            !
                                                            ;
                                                                        \
U!'.JACCEPTA8 LE                                    \\       Ut\i.A.CC:EPTABLE CJPERATIO [\j                                                OPERATION Ll-'----'---.
AGGEPTAJ3LE OPERATIO!'>l
                                                                              \
                                                                                  \
                                                                                    \\
                                                                                      \
                                                                                        \
                -40        -30      -20          0          0      10          20             30       40 Axial Flux Difference NOTES:
: 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                                     TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                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.V' System," Revision 0, Mar 1997.
Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.V' 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 ZIRLO'," 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                                     TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL                                 Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 37 COLR Parameter                     NRC Approved Methodology Section 2.7   Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor (FN,.,H)                   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.
2.8    Axial Flux Difference (AFD)        WCAP-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," September 1974.
NS-TMA-2198, Westinghouse to NRC Letter


==Attachment:==
==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  
  "Operation and Safety Analysis Aspects of an Improved Load Follow Package,"
,1 T and Thermal Overtemperature  
January 31, 1980.
,1 T Trip Functions," September 1986. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower  
NS-CE-687, Westinghouse to NRC Letter, "Power Distribution Control Analysis," July 16, 1975.
,1 T and Thermal Overtemperature  
2.9    Overtemperature ,1T Setpoint      WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"
,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}}
September 1986.
2.10    Overpower ,1T Setpoint            WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"
September 1986.
2.11    RCS Pressure, Temperature, and    WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate      Procedure," April1989, for those events Boiling (DNB) Limits              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.
2.12    Refueling Boron Concentration    WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.
Page 18 of 18}}

Revision as of 22:25, 30 October 2019

Core Operating Limits Report (COLR) Cycle 37 (U1C37)
ML16089A075
Person / Time
Site: Point Beach NextEra Energy icon.png
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


Text

March 29, 2016 NRC 2016-0011 TS 5.6.4 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.

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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 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 (FNllH) 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature L1T Setpoint 2.10 3.3.1 Overpower L1T Setpoint 2.11 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 3.9.1 Refueling Boron Concentration Figure 1 2.1.1 Reactor Core Safety Limits Curve Figure 2 3.1.1 Required Shutdown Margin Figure 3 3.1.6 Control Bank Insertion Limits Figure 4 3.2.1 Hot Channel Factor Normalized Operating Envelope (K(Z))

Figure 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4.

2.1 Reactor Core Safety Limits (TS 2.1.1)

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

Applicability: MODES 1 and 2 2.2 Shutdown Margin (TS 3.1.1 and referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.2.1 SDM shall be ~.0% ~klk (see Figure 2).

Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be :::::1% ~klk.

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

2.3.2 The maximum upper MTC limits shall be:

~5 pcm/°F for power levels ~70% RTP

~0 pcm/°F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 2.5 Control Bank Insertion Limits (TS 3.1.6)

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

The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3.

Applicability: MODE 1 and MODE 2 with keff ::::::1.0 2.6 Nuclear Heat Flux Hot Channel Factor (F0 (Z)) (TS 3.2.1)

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

F0 (Z) ~ CF0

  • K(Z) I P for P > 0.5 F0 (Z) ~ CF0
  • K(Z) I 0.5 for P ~ 0.5 Where P is the fraction of Rated Power at which the core is operating.

F0 (Z) is both:

  • Steady State F0 c(Z) = Fo(Z)
  • 1.08
  • W(Z) I P for P>0.5 F0 w(Z) =F0 c(Z)
  • W(Z) I 0.5 for P_::: 0.5 CF 0 =2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and SA The following F0 penalty factors are applicable to Cycle 37.

Cycle Burnup Fw0 (Z) Penalty (MWD/MTU) Factors BOL to EOL 1.02 Applicability: MODE 1 Page 4 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37

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 ~15% RTP Page 5 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 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 q1 and qb are the percent power in the top and bottom halves of the core respectively, and q1 + 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 q1 - qb exceeds +6 percent, the L1T 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 q1 - qb exceeds -12 percent, the L1T trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.

Applicability: MODES 1 and 2 1

Nominal Setpoint Value 2

Allowable Value Page 6 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 2.10 Overpower ~T Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)

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

~To = indicated ~Tat 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 Pressurizer pressure shall be maintained ::::2205 psig during operation.

NOTE: Pressurizer pressure limit does not apply during:

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

2.11.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained

186,000 gpm.

Applicability: MODE 1 2.12 Refueling Boron Concentration (TS 3. 9. 1)

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

Applicability: MODE 6 1

Nominal Setpoint Value 2

Allowable Value Page 7 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680r------.-------r------.-------,------,------,-----~

Unacceptable Operation 540+-----~-------+------4-------~-----+------~----~

0.0 0.2 OA 0.6 0.8 1.0 1.2 1A Core Power (fraction of 1800 MWt)

Page 8 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 2 REQUIRED SHUTDOWN MARGIN

.3 ..5%

3.0%

2..5%

~

>

"'v

!"'

l.O%

  • ~=

.2"'

=

.?;

0

-:::;

~

L5%

c; 1.0%

o.s%H=

0.0%

0 10 20 30 40 50 60 70 80 90 100 Core Burnup (%)

Page 9 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 3 CONTROL BANK INSERTION LIMITS 240 225 121% I / 168.50% I

/ /

...-... 210 *l Bank B Insertion J /

c /

$: 195 / /

ro / 1§ L-

""0 180 / / /

..c 1176l / v

~ 165 /

1Bank C Insertion J /

(/)

150

// /

c.. /

<I)

........

135 / /

U)

"--""

/

/

v

p c

0

"(j) 120 105 / /

v 0 / VI Bank D Insertion 1-0....

~

c 90 75 v /

v r---

ro /v v co 60 / /

0 /v 45

~~

L-

........

c

()

0 30 /

15 t28.50% v/

I .A' 0

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

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

Page 10 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))

1.2 1.1 1co.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 12 CORE HEIGHT (FI)

Page 11 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 5 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 5 (can't)

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 5A 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE 1oo~r----------r-IT!=--=;:=;:::::::::===;::::::::=~~==::;--,

Pcw*e r Tech Spec Level Envalcpe

=~t ~~~

'11.0 11.0 95

  • 1S.C 1:.Di

{ ~2"1.1} 21.1}

! **2&3J: 2n.n t 31.[} 31.0 90 ...."!'

!

\

U!'.JACCEPTA8 LE \\ Ut\i.A.CC:EPTABLE CJPERATIO [\j OPERATION Ll-'----'---.

AGGEPTAJ3LE OPERATIO!'>l

\

\

\\

\

\

-40 -30 -20 0 0 10 20 30 40 Axial Flux Difference NOTES:

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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.V' System," Revision 0, Mar 1997.

Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.V' 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 ZIRLO'," 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor (FN,.,H) 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.

2.8 Axial Flux Difference (AFD) WCAP-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," 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 ,1T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"

September 1986.

2.10 Overpower ,1T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"

September 1986.

2.11 RCS Pressure, Temperature, and WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate Procedure," April1989, for those events Boiling (DNB) Limits 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.

2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Page 18 of 18

March 29, 2016 NRC 2016-0011 TS 5.6.4 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.

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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 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 (FNllH) 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature L1T Setpoint 2.10 3.3.1 Overpower L1T Setpoint 2.11 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 3.9.1 Refueling Boron Concentration Figure 1 2.1.1 Reactor Core Safety Limits Curve Figure 2 3.1.1 Required Shutdown Margin Figure 3 3.1.6 Control Bank Insertion Limits Figure 4 3.2.1 Hot Channel Factor Normalized Operating Envelope (K(Z))

Figure 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4.

2.1 Reactor Core Safety Limits (TS 2.1.1)

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

Applicability: MODES 1 and 2 2.2 Shutdown Margin (TS 3.1.1 and referenced in TS 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.2.1 SDM shall be ~.0% ~klk (see Figure 2).

Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be :::::1% ~klk.

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

2.3.2 The maximum upper MTC limits shall be:

~5 pcm/°F for power levels ~70% RTP

~0 pcm/°F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 2.5 Control Bank Insertion Limits (TS 3.1.6)

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

The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3.

Applicability: MODE 1 and MODE 2 with keff ::::::1.0 2.6 Nuclear Heat Flux Hot Channel Factor (F0 (Z)) (TS 3.2.1)

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

F0 (Z) ~ CF0

  • K(Z) I P for P > 0.5 F0 (Z) ~ CF0
  • K(Z) I 0.5 for P ~ 0.5 Where P is the fraction of Rated Power at which the core is operating.

F0 (Z) is both:

  • Steady State F0 c(Z) = Fo(Z)
  • 1.08
  • W(Z) I P for P>0.5 F0 w(Z) =F0 c(Z)
  • W(Z) I 0.5 for P_::: 0.5 CF 0 =2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and SA The following F0 penalty factors are applicable to Cycle 37.

Cycle Burnup Fw0 (Z) Penalty (MWD/MTU) Factors BOL to EOL 1.02 Applicability: MODE 1 Page 4 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37

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 ~15% RTP Page 5 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 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 q1 and qb are the percent power in the top and bottom halves of the core respectively, and q1 + 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 q1 - qb exceeds +6 percent, the L1T 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 q1 - qb exceeds -12 percent, the L1T trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.

Applicability: MODES 1 and 2 1

Nominal Setpoint Value 2

Allowable Value Page 6 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 2.10 Overpower ~T Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)

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

~To = indicated ~Tat 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 Pressurizer pressure shall be maintained ::::2205 psig during operation.

NOTE: Pressurizer pressure limit does not apply during:

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

2.11.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained

186,000 gpm.

Applicability: MODE 1 2.12 Refueling Boron Concentration (TS 3. 9. 1)

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

Applicability: MODE 6 1

Nominal Setpoint Value 2

Allowable Value Page 7 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680r------.-------r------.-------,------,------,-----~

Unacceptable Operation 540+-----~-------+------4-------~-----+------~----~

0.0 0.2 OA 0.6 0.8 1.0 1.2 1A Core Power (fraction of 1800 MWt)

Page 8 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 2 REQUIRED SHUTDOWN MARGIN

.3 ..5%

3.0%

2..5%

~

>

"'v

!"'

l.O%

  • ~=

.2"'

=

.?;

0

-:::;

~

L5%

c; 1.0%

o.s%H=

0.0%

0 10 20 30 40 50 60 70 80 90 100 Core Burnup (%)

Page 9 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 3 CONTROL BANK INSERTION LIMITS 240 225 121% I / 168.50% I

/ /

...-... 210 *l Bank B Insertion J /

c /

$: 195 / /

ro / 1§ L-

""0 180 / / /

..c 1176l / v

~ 165 /

1Bank C Insertion J /

(/)

150

// /

c.. /

<I)

........

135 / /

U)

"--""

/

/

v

p c

0

"(j) 120 105 / /

v 0 / VI Bank D Insertion 1-0....

~

c 90 75 v /

v r---

ro /v v co 60 / /

0 /v 45

~~

L-

........

c

()

0 30 /

15 t28.50% v/

I .A' 0

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

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

Page 10 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))

1.2 1.1 1co.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 12 CORE HEIGHT (FI)

Page 11 of 18

POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 5 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 5 (can't)

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 5A 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE 1oo~r----------r-IT!=--=;:=;:::::::::===;::::::::=~~==::;--,

Pcw*e r Tech Spec Level Envalcpe

=~t ~~~

'11.0 11.0 95

  • 1S.C 1:.Di

{ ~2"1.1} 21.1}

! **2&3J: 2n.n t 31.[} 31.0 90 ...."!'

!

\

U!'.JACCEPTA8 LE \\ Ut\i.A.CC:EPTABLE CJPERATIO [\j OPERATION Ll-'----'---.

AGGEPTAJ3LE OPERATIO!'>l

\

\

\\

\

\

-40 -30 -20 0 0 10 20 30 40 Axial Flux Difference NOTES:

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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL 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.V' System," Revision 0, Mar 1997.

Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.V' 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 ZIRLO'," 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 TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 18 March 19, 2016 CORE OPERATING LIMITS REPORT (COLR)

UNIT 1 CYCLE 37 COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor (FN,.,H) 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.

2.8 Axial Flux Difference (AFD) WCAP-8403 (non-proprietary), "Power Distribution Control and Load Following Procedures," 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 ,1T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"

September 1986.

2.10 Overpower ,1T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ,1T and Thermal Overtemperature ,1T Trip Functions,"

September 1986.

2.11 RCS Pressure, Temperature, and WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate Procedure," April1989, for those events Boiling (DNB) Limits 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.

2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

Page 18 of 18

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