NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)
| ML20307A035 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/02/2020 |
| From: | Schultz E Nextera Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2020-0039 | |
| Download: ML20307A035 (20) | |
Text
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POINT BEACH November 2, 2020 NRC 2020-0039 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 40 (U1 C40)
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 40.
The Enclosure to this letter contains the PBNP U1 C40 COLR that was issued on October 13, 2020.
This letter contains no new regulatory commitments and no revisions to existing commitments.
Sincerely, NextEra Energy Point Beach, LLC Eric Schultz Licensing Manager Enclosure cc: Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 5,241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 (U1C40) 18 pages follow
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 REVISION 21
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 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 (FQ(Z))
2.7 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature AT Setpoint 2.10 3.3.1 Overpower AT 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 SA 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 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 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 ITS 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% ~k/k (see Figure 2).
Applicability: MODES 1, 2, and 3 2.2.2 SDM shall be ~1 % ~k/k.
Applicability: MODES 4 and 5 2.3 Moderator Temperature Coefficient ITS 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 ~70% RTP
~O pcm/°F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with keff ~1 .0.
2.4 Shutdown Bank Insertion Limit ITS 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 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 2.5 Control Bank Insertion Limits ITS 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 over1ap limits specified in Figure 3.
Applicability: MODE 1 and MODE 2 with ke!f ~1.0 2.6 Nuclear Heat Flux Hot Channel Factor (Fo(Z)) (TS 3.2.1)
The Heat Flux Hot Channel Factor shall be within the following limits:
FQ(Z) :s; CFQ
- K(Z) / P for P > 0.5 FQ(Z) :s; CFa
- K(Z) / 0.5 for P :s; 0.5 Where Pis the fraction of Rated Power at which the core is operating.
FQ(Z) is both:
- Steady State FaC(Z) = Fa(Z)
- 1.08
- Transient FaW(Z) = FaC(Z)
- W(Z) / P for P>0.5 FaW(Z) = FaC(Z)
- W(Z) / 0.5 for p~ 0.5 CFQ = 2.60 K(Z) is the function in Figure 4 W(Z) is the function in Figures 5 and SA.
The following Fa penalty factors are applicable.
CycleBumup f°NQ(Z) Penalty (MWD/MTU) Factors BOL to< 1621 1.028 1621 to EOL 1.02 Applicability: MODE 1 Page 4 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH} as 3.2.2)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7.1 FNAH :s;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 CAFD) CTS 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 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 2.9 Overtemperature L\T Setpoint ITS 3.3.1 , Table 3.3.1-1 note 1)
Overtemperature L\T setpoint parameter values (for 1800 Mwt core power):
L\To = indicated L\T at RTP, °F T = indicated RCS average temperature, °F T' ~ 576.0°F p = pressurizer pressure, psig P' ~ 2235 psig K1 ~ 1.170 (NTSP) 1 K1 ~ 1.183 (AV) 2 K2 ~ 0.016 i<3 ~ 0.000811
't1 = 40sec
't2 = 8 sec
't3 = 4sec
't4 = 2 sec for Rosemount RTDs
- 0. 75 sec for Ultra Electronics RTDs
't4 f(L\I) 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 qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RTP, such that:
2.9.1 For qt - qb within -12, +6 percent, f(L\I) = 0.
2.9.2 For each percent that the magnitude of qt - qb exceeds +6 percent, the L\T trip setpoint shall be automatically reduced by an equivalent of 2.00 percent of Rated Power.
2.9.3 For each percent that the magnitude of qt* qb exceeds -12 percent, the L\T 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 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 2.10 Overpower AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)
Overpower AT setpoint parameter values (for 1800 Mwt core power):
ATo = indicated AT at RTP, °F T = indicated RCS average temperature, °F T' ~ 576.0°F
~ ~ 1.083 (NTSP)1
~ ~ 1.096 (AV)2 Ks ~ 0.0 for increasing T Ks = 0.0 for decreasing T Ks ~ 0.00123 for T ~ T' Ks = 0.0 forT < T' t5 ~ 0sec t3 = 4 sec t4 = 2 sec for Rosemount RTDs t4 < 0.75 sec for Ultra Electronics RTDs Applicability: MODES 1 and 2 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits as 3.4.11 2.11 .1 Tavg shall be ~577°F.
2.11.2 Pressurizer pressure shall be maintained ~205 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 ~350 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 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680 - , - - - - - - - . - - - - . . - - - - - - - - . - - - - - , - - - - - - - - . - - - - . - - - - - - ,
2425 psia Unacceptable Operation f
-:::I E
e Cl)
{!:.
620 +-- ~-.d-- - - + -~....,-- + - - - + -___,,- ---+- - - + - - - - ----1 Cl)
C)
!c. Acceptable Operation 600 + - - - - - - + - - - - + - - - - - - + - - --"'-.!--------""-.- 1------- ~ - + - - - - ---I 0
0
...J IJ)
Cl)
..c:
C)
- c 540 + - - - - - + - - - - + - - - - - + - - - - + - - - - - + - - - - + - - - - - - - I 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 Core Power (fraction of 1800 MWt)
Page 8 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE2 REQUIRED SHUTDOWN MARGIN 3
- 0. ,
0 ]0 20 30 0 0 7 80 0 100 r l\11111u1> I Page 9 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE3 CONTROL BANK INSERTION LIMITS 240 225 ,, II21% II ./
! 68.50% !
-~
C 210 195 /
_/
V
~
/
... : Bank B Insertion :
/"
/
V 1~ .,.
"C 180 / V
.c J 115 I /
/
V
~ 165
.,.V 11' 1 Bank C Insertion i V
(/J 150 /
- a. V /II'
.m
_/
C/'J 135 V C 120 / V 0
- w 105
/" , V 0
- a. 90 V .,.v I Bank D Insertion I
~
C 75 V V
/
V a,
m 60 / .,./ /
e /v
.....C 45 ~ 1 I 0
(.) 30 I/
15 i 2a.5o% I/ V I r O O 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 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
1.2 1.1 I(o.o, 1.0)I 1(6.0, 1.0)1 jc12.o, 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 11 12 CORE HEIGHT (FI)
Page 11 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURES Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
W(Z)
Height (feet) 150 1000 6000 8000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 0.2 1.0000 1.0000 1.0000 1.0000 1.0000 0.4 1.0000 1.0000 1.0000 1.0000 1.0000 0.6 1.0000 1.0000 1.0000 1.0000 1.0000 0.8 1.0000 1.0000 1.0000 1.0000 1.0000 1.0 1.0000 1.0000 1.0000 1.0000 1.0000 1.2 1.0000 1.0000 1.0000 1.0000 1.0000 1.4 1.0876 1.0887 1.0982 1.1021 1.1100 1.6 1.0888 1.0899 1.0987 1.1022 1.1091 1.8 1.0899 1.0908 1.0989 1.1019 1.1077 2.0 1.0906 1.0915 1.0986 1.1012 1.1057 2.2 1.0912 1.0919 1.0980 1.1001 1.1032 2.4 1.0915 1.0922 1.0971 1.0986 1.1003 2.6 1.0917 1.0922 1.0958 1.0968 1.0971 2.8 1.0916 1.0920 1.0942 1.0946 1.0935 3.0 1.0913 1.0915 1.0923 1.0922 1.0895 3.2 1.0908 1.0908 1.0902 1.0894 1.0858 3.4 1.0901 1.0899 1.0880 1.0864 1.0833 3.6 1.0892 1.0888 1.0860 1.0838 1.0824 3.8 1.0879 1.0874 1.0838 1.0819 1.0826 4.0 1.0868 1.0859 1.0817 1.0809 1.0829 4.2 1.0858 1.0845 1.0803 1.0806 1.0830 4.4 1.0846 1.0831 1.0796 1.0803 1.0830 4.6 1.0833 1.0816 1.0791 1.0798 1.0828 4.8 1.0817 1.0800 1.0784 1.0793 1.0824 5.0 1.0799 1.0781 1.0775 1.0785 1.0820 5.2 1.0780 1.0761 1.0765 1.0775 1.0816 5.4 1.0761 1.0739 1.0753 1.0764 1.0809 5.6 1.0740 1.0715 1.0738 1.0753 1.0798 5.8 1.0717 1.0692 1.0721 1.0743 1.0785 6.0 1.0690 1.0667 1.0700 1.0732 1.0768 Page 12 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE 5 (con't)
Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
W(Z)
Height (feet) 150 1000 6000 8000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0663 1.0638 1.0680 1.0717 1.0747 6.4 1.0637 1.0608 1.0666 1.0698 1.0722 6.6 1.0612 1.0589 1.0649 1.0677 1.0705 6.8 l.0585 1.0580 1.0622 1.0642 l.0729 7.0 1.0572 1.0572 1.0620 1.0650 1.0773 7.2 1.0561 1.0563 1.0654 1.0700 1.0806 7.4 1.0550 1.0562 1.0701 1.0741 1.0837 7.6 1.0591 1.0613 1.0745 1.0781 1.0864 7.8 1.0647 1.0669 1.0785 1.0818 l.0887 8.0 1.0700 1.0719 1.0823 1.0852 1.0905 8.2 1.0752 1.0769 1.0858 1.0883 1.0920 8.4 1.0804 1.0817 1.0889 1.0911 1.0931 8.6 1.0853 1.0863 1.0918 1.0936 1.0939 8.8 l.0900 1.0907 1.0942 1.0957 l.0943 9.0 1.0946 1.0948 1.0967 1.0975 1.0944 9.2 1.0989 1.0987 1.0991 1.0989 1.0942 9.4 1.1030 1.1022 1.1012 1.0999 1.0938 9.6 1.1068 1.1055 1.1032 1.1004 1.0934 9.8 1.1103 1.1084 1.1049 1.1012 1.0929 10.0 1.1136 1.1113 1.1064 1.1017 1.0923 10.2 1.1167 1.1143 1.1073 1.1026 1.0912 10.4 1.0000 1.0000 1.0000 1.0000 1.0000 10.6 1.0000 1.0000 1.0000 1.0000 1.0000 10.8 1.0000 1.0000 1.0000 1.0000 1.0000 11.0 1.0000 1.0000 1.0000 1.0000 1.0000 11.2 1.0000 1.0000 1.0000 1.0000 1.0000 11.4 1.0000 1.0000 1.0000 1.0000 1.0000 11.6 1.0000 1.0000 1.0000 1.0000 1.0000 11.8 1.0000 1.0000 1.0000 1.0000 1.0000 12.0 1.0000 1.0000 1.0000 1.0000 1.0000 Page 13 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE SA BOC Part-Power Summary of W(Z) as a Function of Core Height (D-Bank ~ 205 steps)
(Top 15% and Bottom 12% Excluded)
Part-Power W(Z) with Correction Factor Height (feet) (excludine nower 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 1.1767 1.6 1.1750 1.8 1.1733 2.0 1.1699 2.2 1.1657 2.4 1.1615 2.6 1.1575 2.8 1.1535 3.0 1.1493 3.2 1.1447 3.4 1.1395 3.6 1.1342 3.8 1.1289 4.0 1.1244 4.2 1.1200 4.4 1.1147 4.6 1.1088 4.8 1.1025 5.0 1.0962 5.2 1.0899 5.4 1.0836 5.6 1.0771 5.8 1.0702 6.0 1.0628 Page 14 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE SA (con't)
BOC Part-Power Summary of W(Z) as a Function of Core Height (D-Bank ~ 205 steps)
(Top 15% and Bottom 12% Excluded)
Part-Power W(Z) with Correction Factor Height (feet) (excludine nower ratio) 75%Power 6.2 1.0553 6.4 1.0481 6.6 1.0410 6.8 1.0338 7.0 1.0280 7.2 1.0224 7.4 1.0170 7.6 1.0167 7.8 1.0177 8.0 1.0183 8.2 1.0189 8.4 1.0197 8.6 1.0204 8.8 1.0207 9.0 1.0204 9.2 1.0204 9.4 1.0211 9.6 1.0221 9.8 1.0234 10.0 1.0254 10.2 1.0278 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 Revilion 21 Oclober 131 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 FIGURE 8 FWX DIFFERENCE OPERATING ENVELOPE P IJWl'l'r Ta-ch Spec Level Envalop,e UNACCEPTABLE UNA CCEPTABLE OPEAAT I0N O PERA ION
~
0 Q)
ACCEPTABLE OPERAT ION
~
a.. 7
-0
.sw a:::
--40 -30 -20 -10 0 10 20 30 40 Axia t Flux o *fference NOTES:
- 1) 1h11 llgUl"9 n,pn,unta the COnttant.Axlal onaet central (CAOC} band used In aately analyaea, It mrq be admininativaly tightened depending on in-core flux map nMlulm. Refer to Figura 2 of Reactor Openlting Data (RO) 1.2 for the adm~lltratlVe llmll
- 2) The AFD may dsv1ate outalde the target band with n-lERMAL POVVER < 60% RTP.
- 3) Toa AFD target band i9 +/-6% for THERMAL POWER 2=15% RTP.
Paga 16 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 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' System," Revision 0, Mar 1997.
Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-BOP: Basis for a Power Uprate With the LEFM' 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 (Fo(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-10054-P-A, 'Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.
WCAP-10054-P-A, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model,"
Addendum 2, Revision 1, July 1997.
Page 17 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 21 October 13, 2020 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 40 COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor (FNAH) 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 AT Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature .1.T Trip Functions,"
September 1986.
2.10 Overpower .1.T Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
2.11 RCS Pressure, Temperature, and WCAP-11397-P-A, "Revised Thermal Design Flow Departure from Nucleate Procedure, 11 April 1989, 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), 11 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