Text

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

March 29, 2016 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

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.

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