NRC 2018-0051, Core Operating Limits Report (COLR) Unit 2 Cycle 37 (U2C37)
| ML18310A044 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/06/2018 |
| From: | Schultz E Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2018-0051 | |
| Download: ML18310A044 (20) | |
Text
ENERGY POINT BEACH November 6, 2018 NRC 2018-0051 TS 5.6.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 2 Docket No. 50-301 Renewed License No. DPR-27 Core Operating Limits Report (COLR) Unit 2 Cycle 37 (U2C37)
In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.4, enclosed is TRM 2.1, COLR, Unit 2, Cycle 37.
The Enclosure to this letter contains the PBNP U2C37 COLR that was issued on October 13, 2018.
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 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 2 CORE OPERATING LIMITS REPORT {COLR)
UNIT 2 CYCLE 37 {U2C37) 18 pages follow
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 REVISION 20
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 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 (FN ~'>H) 2.8 3.2.3 Axial Flux Difference (AFD) 2.9 3.3.1 Overtemperature ~ T Setpoint 2.10 3.3.1 Overpower ~ T Setpoint 2.11 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 3.9.1 Refueling Boron Concentration Figure 1 2.1.1 Reactor Core Safety Limits Curve Figure 2 3.1.1 Required Shutdown Margin Figure 3 3.1.6 Control Bank Insertion Limits Figure 4 3.2.1 Hot Channel Factor Normalized Operating Envelope (K(Z))
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 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 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 :2':2.0% Llklk (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 pcmrF for power levels
- :;?0% RTP
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 :2':225 steps.
Applicability: MODES 1 and 2 Page 3 of 18*
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 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 2':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:
F0 (Z) ~ CFQ
- K(Z) I P for P > 0.5 F0 (Z) ~ CFQ
- 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 FQ penalty factors are applicable.
Cycle Burnup Fvva(Z) Penalty (MWD/MTU) Factors SOL to< 1474 1.026 1474 to EOL 1.02 Applicability: MODE 1 Page 4 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 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 FNAH ~1.68 X [1 + 0.3(1-P)]
where: P is the fraction of Rated Power at which the core is operating.
Applicability: MODE 1 2.8 Axial Flux Difference (AFD) (TS 3.2.3)
The AFD target band is +/-5%.
The AFD Acceptability Operation Limits are provided in Figure 6.
Applicability: MODE 1 with THERMAL POWER ~15% RTP 2.9 Overtemperature ~T Setpoint (TS 3.3.1, Table 3.3.1-1 note 1)
Overtemperature ~T setpoint parameter values (for 1800 MWt core power):
~To = indicated~Tat RTP, oF T = indicated RCS average temperature, oF T' ~ 576.0°F p = pressurizer pressure, psig P' ~ 2235 psig K1 ~ 1.170 (NTSP) 1 K1 ~ 1.183 (AV) 2 Kz ~ 0.016 K3 ~ 0.000811 T1 = 40 sec Tz = 8 sec T3 = 4 sec T4 = 2 sec f(~l) 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 q1+ qb is total core power in percent of RTP, such that:
1 Nominal Setpoint Value 2
Allowable Value Page 5 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 2.9.1 For q1 - qb within -12, +6 percent, f(~l) = 0.
2.9.2 For each percent that the magnitude of q1 - qb exceeds +6 percent, the~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 q1 - qb exceeds -12 percent, the~ T trip setpoint shall be automatically reduced by an equivalent of 2.69 percent of Rated Power.
Applicability: MODES 1 and 2 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, oF T' :=:; 576.0oF Kt :=:; 1. 083 (NTSP) 1 Kt :=:; 1.096 (AV) 2 Ks ~ 0.0 for increasing T Ks = 0.0 for decreasing T K6 ~ 0.00123 forT_:: T' K6 = 0.0 forT< T'
'!:5 ~ 0 sec
'!:3 = 4 sec
'!:4 = 2 sec Applicability: MODES 1 and 2 1
Nominal Setpoint Value 2
Allowable Value Page 6 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 2.11 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.11.1 Tavg shall be :s;57rF.
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 Page 7 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE 680.------,-------r------~------r-----~------~------,
Unacceptable Operation
(!)
- J
+-'
<U
....(!)
E620+-~-=~~~~~~~~+-~~~~~~~~~~~~~~
(!)
1-(!)
Cl
<U
(!)
<(
~600+-~~~~~~~~~~+-~~~~~~~~~~
0 0
....1
+-'
1/)
(!)
..c Cl
- c 540+------4------~------+-------~-----+------~----~
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 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE2 REQUIRED SHUTDOWN MARGIN JSI>
~.0%
2.5%
'Ii
- ~
2.0%
~
-~
2
~ l-5'~
Q
~
l.O%
os:~
0,0%
Core Burnup (%}
Page 9 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE 3 CONTROL BANK INSERTION LIMITS 240 I I 225 121% I / 168.50% I
/ /
........_ 210 /
c
- /
v *: Bank B Insertion I
/
-o ro
..c 195 180 /
/
/
v 18If
/
~ 165 [176l /
/ 1Bank C Insertion 1 /
CJ) 0.. 150 /
/
Q)
...... / /
(f) 135
/
/
v E
c 0
120 105 / v CJ) 0 v /I Bank D Insertion~
0...
~
c 90 75 v v
/
v
~
CQ ro / /
60 0
/ /v c
0 45
~:J /
0 30 15 I 28.50% 1/
/
0 I I X 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 ;:c: 225 steps (Limits are always considered met when withdrawn position is ;:c: 225 steps).
Page 10 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
1.2 1.1 1(0.0, 1.0) 1 (6.0, l.l)) 1 11 (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 (FT)
Page 11 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE 5 Summary of W(Z) as a Function of Core Height (Top 15% and Bottom 12% Excluded)
W Z)
Height (feet) 150 1000 6000 16000 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 1.0874 1.0883 1.0977 1.1037 1.6 1.0885 1.0894 1.0982 1.1032 1.8 1.0895 1.0903 1.0984 1.1023 2.0 1.0903 1.0910 1.0983 1.1009 2.2 1.0908 1.0915 1.0977 1.0990 2.4 1.0912 1.0917 1.0968 1.0968 2.6 1.0913 1.0918 1.0956 1.0942 2.8 1.0912 1.0916 1.0941 1.0914 3.0 1.0909 1.0912 1.0924 1.0886 3.2 1.0904 1.0905 1.0903 1.0859 3.4 1.0896 1.0896 1.0880 1.0837 3.6 1.0886 1.0885 1.0855 1.0823 3.8 1.0874 1.0874 1.0833 1.0817 4.0 1.0861 1.0863 1.0819 1.0813 4.2 1.0847 1.0850 1.0809 1.0806 4.4 1.0835 1.0835 1.0795 1.0801 4.6 1.0821 1.0819 1.0781 1.0806 4.8 1.0806 1.0801 1.0765 1.0808 5.0 1.0789 1.0781 1.0750 1.0807 5.2 1.0771 1.0759 1.0738 1.0804 5.4 1.0751 1.0735 1.0726 1.0797 5.6 1.0728 1.0709 1.0712 1.0787 5.8 1.0704 1.0683 1.0696 1.0773 6.0 1.0680 1.0656 1.0676 1.0755 Page 12 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 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 1000 6000 16000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 6.2 1.0657 1.0629 1.0657 1.0735 6.4 1.0636 1.0602 1.0646 1.0707 6.6 1.0616 1.0584 1.0635 1.0671 6.8 1.0598 1.0576 1.0619 1.0692 7.0 1.0581 1.0568 1.0611 1.0735 7.2 1.0563 1.0563 1.0620 1.0768 7.4 1.0553 1.0568 1.0670 1.0799 7.6 1.0579 1.0620 1.0714 1.0826 7.8 1.0627 1.0676 1.0756 1.0850 8.0 1.0680 1.0726 1.0796 1.0871 8.2 1.0730 1.0777 1.0834 1.0889 8.4 1.0779 1.0825 1.0869 1.0903 8.6 1.0827 1.0872 1.0902 1.0915 8.8 1.0874 1.0916 1.0932 1.0923 9.0 1.0919 1.0958 1.0961 1.0930 9.2 1.0963 1.0997 1.0988 1.0935 9.4 1.1004 1.1033 1.1014 1.0937 9.6 1.1043 1.1066 1.1036 1.0937 9.8 1.1079 1.1096 1.1055 1.0934 10.0 1.1113 1.1126 1.1072 1.0931 10.2 1.1144 1.1156 1.1083 1.0924 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 1'3 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 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) (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 1.1759 1.6 1.1729 1.8 1.1702 2.0 1.1666 2.2 1.1625 2.4 1.1587 2.6 1.1550 2.8 1.1510 3.0 1.1466 3.2 1.1421 3.4 1.1372 3.6 1.1321 3.8 1.1270 4.0 1.1222 4.2 1.1171 4.4 1.1118 4.6 1.1059 4.8 1.1000 5.0 1.0939 5.2 1.0879 5.4 1.0817 5.6 1.0752 5.8 1.0683 6.0 1.0612 Page 14 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE SA (can't)
BOG Part-Power Summary of W(Z) as a Function of Core Height (D-Bank :s:; 205 steps)
(Top 15% and Bottom 12% Excluded)
Part-Power W(Z) with Correction Factor Height (feet) (excluding_l)_ower rati<J}_
75% Power 6.2 1.0541 6.4 1.0475 6.6 1.0413 6.8 1.0352 7.0 1.0290 7.2 1.0228 7.4 1.0174 7.6 1.0157 7.8 1.0161 8.0 1.0170 8.2 1.0176 8.4 1.0183 8.6 1.0191 8.8 1.0197 9.0 1.0202 9.2 1.0208 9.4 1.0216 9.6 1.0227 9.8 1.0238 10.0 1.0256 10.2 1.0279 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 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE UNAC(~EP fA.EJLE !Jf\fb.t':fE:P Lti,R t E
\J!'--'rRA Tl(JN OPE.Rt\TlON
+~C;CEFtT.AJ3LE OPEf!A.T!()N 10 0 10 Axial NOTE:
- 1. This figure represents the Constant Axial Offset Control (CAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results.
Refer to Figure 2 of Reactor Operating Data (ROD) 1.2 for the administrative limit.
- 2. The AFD may deviate outside the target band with THERMAL POWER< 50% RTP.
- 3. The AFD target band is +/-5% for THERMAL POWER;:: 15% RTP.
Page 16 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section All Reactor Thermal Output Caldon, Inc., Engineering Report-SOP, "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM" System," Revision 0, Mar 1997.
Caldon, Inc., Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM" System," Revision 0, May 2000.
WCAP-12610-P-A, "VANTAGE+ Fuel Assembly 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 (F0 (Z)) Control and Load Following Procedures,"
Westinghouse Electric Corporation, September 1974.
WCAP-14449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision 1, October 1999 (cores containing 422V +fuel).
WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.
WCAP-1 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.
WCAP-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 U2 TECHNICAL REQUIREMENTS MANUAL Revision 20 October 13, 2018 CORE OPERATING LIMITS REPORT (COLR)
UNIT 2 CYCLE 37 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot WCAP-9272-P-A, "Westinghouse Reload Safety Channel Factor (FN AH) Evaluation Methodology," July 1985.
WCAP-16259-P-A, "Westinghouse Methodology for Applications of 3-D Transient Neutronics to Non-LOCA Accident Analysis," August 2006.
2.8 Axial Flux Difference (AFD) WCAP-8403 (nonproprietary), "Power Distribution Control and Load Following Procedures,"
Westinghouse Electric Corporation, September 1974.
NS-TMA-2198, Westinghouse to NRC Letter
Attachment:
"Operation and Safety Analysis Aspects of an Improved Load Follow Package," January 31, 1980.
NS-CE-687, Westinghouse to NRC Letter, "Power Distribution Control Analysis," July 16, 1975.
2.9 Overtemperature ~ T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower~ T and Thermal Overtemperature ~ T Trip Functions," September 1986 2.10 Overpower ~ T Setpoint WCAP-87 45-P-A, "Design Bases for the Thermal Overpower ~ T and Thermal Overtemperature ~ T Trip Functions," September 1986 2.11 RCS Pressure, Temperature, WCAP-11397 -P-A, "Revised Thermal Design and Flow Departure from Procedure," April 1989, for those events analyzed Nucleate Boiling (DNB) Limits using RTDP WCAP-14787-P, Rev. 3, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Point Beach Units 1 & 2 Power Uprate (1775 MWt Core Power with Feedwater Venturis, or 1800 MWt Core Power with LEFM on Feedwater Header)", February 2009.
WCAP-9272-P-A, "Westinghouse Reioad 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