NRC 2010-0041, Cycle 33 (U1C33) Core Operating Limits Report
| ML100810215 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/22/2010 |
| From: | Jim Costedio Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2010-0041 | |
| Download: ML100810215 (20) | |
Text
TM POINT BEACH March 22,2010 NRC 2010-0041 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 Unit ICvcle 33 (UlC33) Core Operating Limits Report In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.4, "Core Operating Limits Report (COLR),"
NextEra Energy Point Beach, LLC (NextEra) is submitting the Core Operating Limits Report for PBNP Unit ICycle 33 (UlC33).
The enclosure to this letter contains the PBNP UlC33 COLR that was issued on March 17,2009.
This letter contains no new regulatory commitments and no revisions to existing commitments.
Very truly yours, NextEra Energy Point Beach, LLC James Costedio Licensing Manager Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC,6610 Nuclear Road, Two Rivers, WI 54241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNlT 1 CORE OPERATING LIMITS REPORT (COLR)
UNlT I CYCLE 33 (UlC33) 18 pages follow
TRM 2.1 CORE OPERAT NG LIM TS REPORT (COLR)
UNIT 1 CYCLE 33 REVISION 12
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR) 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:
PBNP 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 lnsertion Limits 3.1.6 Control Bank lnsertion Limits 3.1.8 Physics Test Exceptions 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank lnsertion Limit 3.1.6 Control Bank lnsertion Limits 3.2. I Nuclear Heat Flux Hot Channel Factor (FQ(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F*~H) 3.2.3 Axial Flux Difference (AFD) 3.3.1 Overtemperature AT Setpoint 3.3. I Overpower AT Setpoint 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration Figure 1 Reactor Core Safety Limits Curve Figure 2 Required Shutdown Margin Figure 3 Control Bank lnsertion Limits I Figure 4 Hot Channel Factor Normalized Operating Envelope (K(Z)) for 422V+ Fuel Figure 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
I Figure 5A BOC Part-Power RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
Figure 6 Flux Difference Operating Envelope Page 2 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section I.O 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 Safetv Limits (TS 2. I.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 I.
Applicability: MODES 1 and 2 2.2 Shutdown Margin (TS 3.1.Iand referenced in TS 3.1.4, 3.1.5, 3. I.6, and 3.1.8) 2.2.1 SDM shall be within the limits provided in Figure 2.
Applicability: MODES I,2, and 3 2.2.2 SDM shall be 21% Auk.
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:
55 pcml°F for power levels 570% RTP 50 pcml°F for power levels >70% RTP Applicability: MODE Iand MODE 2 with bfi21.O.
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 2228 steps.
Applicability: MODES 1 and 2 Page 3 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 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 kefi> .0I 2.6 Nuclear Hea The Heat Flux Hot Channel Factor shall be within the following limits:
FQ(Z)5 CFQ* K(Z) / Pfor P > 0.5 FQ(Z)5 CFQ* K(Z) / 0.5 for P 5 0.5 Where P is the fraction of Rated Power at which the core is operating.
FQ(Z)is both:
e Steady State FQ'(Z) = FQ(Z)* 1.08 e Transient F ~ ~ ( =z F~'(Z)
)
- W(Z) / P for P>0.5 F ~ ~ ( =z F~'(Z)
)
- W(Z) / 0.5 for P5 0.5 CFQ= 2.60 (422V+ Fuel)
K(Z) is the function in Figure 4.
NOTE: The W(Z) factors in Figure 5 are based on steady state Fq at 100% power.
W(Z) is the function in Figure 5 and 5A.
The following FQpenalty factors are applicable to Cycle 33, F ~ , ( Z )Penalty Cycle Burnup (MWD/MTU)
Factors 150 to 400 1.0200 526 1.0203 651 1.0210 776 1.0213 901 1.0212 1026 1.0203 1151 1.0200 1152 to End-of-Cycle 1.0200 Applicability: MODE 1 Page 4 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 2.7 Nuclear Enthal~vRise Hot Channel Factor (F~.H) (TS 3.2.2)
The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7.1 F~AH < I .77 x [ I + 0.3(1-P)] (422V+ Fuel) 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)
NOTE: The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.
The indicated axial flux difference in % flux difference units shall be maintained within the allowed operational space defined by Figure 6.
Applicability: MODE 1 with THERMAL POWER 250% RTP 2.9 Overtem~eratureAT Set~oint(TS 3.3.1, Table 3.3.1-1 note 1)
Overtemperature AT setpoint parameter values:
indicated AT at Rated Power, OF average temperature, OF 569.0°F 2235 psig 1.16 0.0149 0.00072 25 sec 3 sec 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD f(Al) is an even 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 q b are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of Rated Power, such that:
Page 5 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 2.9.1 For qt - qb within -12, +5 percent, f(Al) = 0.
2.9.2 For each percent that the magnitude of qt - qb exceeds +5 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.12 percent of Rated Power.
2.9.3 For each percent that the magnitude of q, - qb exceeds -12 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of Rated Power.
Applicability: MODES 1 and 2
- 2. I 0 Overpower AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 2)
Overpower AT setpoint parameter values:
indicated AT at Rated Power, OF average temperature, OF 569.0°F 1.10 of Rated Power 0.0262 for increasing T 0.0 for decreasing T 0.00103 for T 2 T' 0.0 for T .= T' 10 sec 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD Applicability: MODES Iand 2 2.1 1 RCS Pressure, Temperature, and Flow De~arturefrom Nucleate Boiling (DNB) Limits (TS 3.4.1)
- 2. I1.1 Tavgshall be 1574OF.
2.1 1.2 Pressurizer pressure shall be maintained 22205 psig during operation.
NOTE: Pressurizer pressure limit does not apply during:
- 1) THERMAL POWER ramp >5% RTP per minute; or
- 2) THERMAL POWER step >lo% RTP.
2.11.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 2182,400 gpm.
Applicability: MODE 1 Page 6 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT ICYCLE 33 2.12 Refuelinn Boron Concentration (TS 3.9.11 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained 22200 ppm.
Applicability: MODE 6
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 FIGURE I REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V + fuel) 680 -
Unacceptable Operation Acceptable Operation 560 - -
5 4 0 i 3 ~ ~ : ' t ' : ' f ' : " ' ~ " ' ! ' k k ~ " '
0 0.2 0.4 0.6 0.8 1 1.2 1.4 Core Power (fraction of 1540 MWt)
Page 8 of 18
h
'fi-N .iij r z -5 2 E22
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 FIGURE 3 CONTROL BANK INSERTION LIMITS NOTE: The "fully withdrawn" parking position range 2 225 steps can be used without violating this Figure.
Page 10 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
FOR 422V+ FUEL 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE EEIGHT (FX?
Page 11 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 FIGURE 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Height W(Z)
(feet) 150 2000 8000 16000 MWDIMTU MWDIMTU MWDIMTU MWDIMTU 0.0 I.oooo 1.oooo 1.oooo 1.oooo 0.2 1.oooo 1.oooo I.oooo 1.oooo 0.4 I.OOOO 1.OOOO 1.OOOO 1.OOOO 0.6 I.OOOO 1.OOOO 1.OOOO 1.OOOO 0.8 I.OOOO 1.0000 I.OOOO 1.0000 1.o 1.oooo I.oooo I.oooo 1.oooo 1.2 1.oooo I.oooo 1.oooo 1.oooo 1.4 1.OOOO 1.OOOO I.OOOO 1.OOOO 1.6 1.2883 1.2436 1.1691 1.1652 I.8 1.2712 1.2276 1.1572 1.1554 2.0 1.2527 1.2102 1.1441 1.1448 2.2 1.2333 1.1921 1.1304 1.1336 2.4 1.2135 - 1.1737
-- 1.1167 1.1224 2.6 1.1937 1.1575 1.1031 1.1112 2.8 1.1743 1.1493 1.0894 1.a998 3.0 1.1621 1.1419 1.0813 1.0927 3.2 1.1576 1.1356 1.0789 1.0912 3.4 1.1562 1.1325 1.0789 1.0913 3.6 1.1538 1.1293 I.0790 1.0915 3.8 1.1511 1.1259 1.0792 I.0945 4.0 I.I480 1.1216 1.0794 1.0984 4.2 1.1444 1.1183 1.0797 1.1018 4.4 1.1404 1.1166 1.0799 1.1050 4.6 1.1358 1.1143 1.0804 1.1077 4.8 1.1308 1.1115 I.0821 1.1099 5.0 1.I252 1.1084 1.0841 1.1116 5.2 1.1192 1.1048 1.a852 1.1129 5.4 1.1126 1.1007 I.0866 1.1134 5.6 1.1054 1.0961 1.0900 1.1150 5.8 1.1020 1.0951 1.0947 1.1257 6.0 1.1039 1.0983 1.1050 1.1408 6.2 1.1113 1.1053 1.1189 I. 1547 6.4 1.1165 1.1110 1.1314 1.1676 6.6 1.1210 1.1181 1.1432 1.1794 6.8 1.1269 1.1245 1.1540 1.1898 Page 12 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 FIGURE 5 (con't)
RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Height - W(Z)
(feet) 150 2000 8000 16000 MWDIMTU MWDIMTU MWDIMTU MWDIMTU 7.0 1.1326 1.1314 1.1638 1.1987 7.2 1.1370 1.1389 1.1723 1.2061 7.4 I.I405 1.1453 1.1795 1.2119 7.6 1.I427 1.1508 1.1854 1.2158 7.8 1.1438 1.1552 1.1897 1.2179 8.0 1.I436 1.1584 1.1925 I.2180 8.2 I.I420 1.1604 1.1936 1.2162 8.4 1.1391 1.1611 1.1930 1.2123 8.6 1.1350 1.1605 1.1907 I.2061 8.8 1.1279 1.1582 I.1858 1.2013 9.0 1.1261 1.1564 1.1851 1.1997 9.2 1.1353 1.1570 1.1895 1.1970 9.4 1.1515 1.1678 1.2028 1.1927 9.6 1.1665 1.1872 1.2158 1.2006 9.8 1.1843 1.2062 1.2327 1.2116 10.0 1.2016 1.2263 1.2499 1.2215 10.2 1.2169 1.2472 1.2637 1.2304 1.oooo I.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo I.oooo I.oooo I.oooo I.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 11.2 I.oooo 1.oooo I.oooo I.oooo II.4 1.oooo 1.oooo 1.oooo 1.oooo 11.6 1.OOOO 1.OOOO 1.OOOO 1.OOOO 11.8 1.OOOO 1.OOOO 1.OOOO I.OOOO 12.0 1.oooo 1.oooo 1.oooo 1.oooo Page 13 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
FIGURE 5A BOC Part-Power RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Height Part Power W(Z) with Correction Factor (excluding power ratio)
(feet) Hot Full 30% 40% 50% 60% 70% 75% 80%
Power Power Power Power Power Power Power Power 0.0 I.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo I' 0.2 1.oooo I.oooo 1.oooo 1.oooo I.oooo 1.oooo 1.oooo 1.oooo 1 0.4 1.OOOO 1.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO 1.OOOO 1.OOOO 1 0.6 I.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO 1 0.8 1.0000 I.OOOO 1.OOOO I.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO I 1.0 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo I.oooo 1.oooo 1.oooo 1 1.2 I.oooo I.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1 1.4 I.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO I.OOOO 1.0000 1.OOOO 1 1.6 1.2883 1.5749 1.5110 1.4606 1.4178 1.3792 1.3598 1.3408 1 1.8 1.2712 1.5349 1.4767 1.4305 1.3913 1.3553 1.3372 1.3195 1 2.0 I.2527 1.4948 1,4419 1.3997 I.3635 1.3303 1.3133 1.2968 1 2.2 1.2333 1.4547 1.4068 1.3684 1.3352 I.3045 1.2888 I.2736 1 2.4 1.2135 1.4150 1.3719 1.3370 1.3067 I.2786 1.2641 I.2501 1, 2.6 1.1937 1.3765 1.3377 1.3062 1.2786 1.2529 1.2397 I.2267 1 2.8 1.1743 1.3391 1.3044 1.2761 1.2512 1.2279 1.2160 1.2040 1 3.0 1.1621 1.3105 1.2795 1.2542 1.2316 1.2105 1.1998 1.1886 1 3.2 1.1576 1.2907 1.2634 I.2405 1.2201 1.2008 1.I912 1.1810 1, 3.4 1.1562 1.2746 1.2509 1.2303 I.2120 I.I 944 1.I858 1.1766 1 3.6 1.1538 1.2591 1.2377 1.2195 1.2033 1.1876 1.1796 1.1716 1 3.8 1.1511 1.2450 1.2265 1.2107 1.1963 1.1818 1.1744 1.1667 1 4.0 1.1480 1.2307 1.2149 1.2015 1.1886 1.1755 1.1687 1.1614 1 4.2 1.1444 1.2156 1.2027 1.1912 1.1800 1.1683 1.1622 1.1555 1 4.4 1.1404 1.2000 1.1901 1.1800 1.1704 1.1601 1.1550 1.1492 1, 4.6 1.1358 1.1840 1.1767 1.1683 1.1602 1.1514 1.1472 1.1422 1 4.8 1.1308 1.1675 1.1623 1.1561 1.1494 1.1423 1.1386 1.1345 I 5.0 1.1252 1.1507 1.1474 1.1433 1.1380 1.1326 1.1294 1.1261 1 5.2 1.1192 1.1340 1.1325 .1.1305 1.1266 1.1226 1.1201 1.1175 1 5.4 1.1126 1.1170 1.1176 1.1173 1.1148 1.1120 1.1102 1.1084 1 5.6 1.1054 1.0998 1.1021 1.1035 1.1024 1.1008 1.0997 1.0986 1 5.8 1.1020 1.0864 1.0906 1.0933 1.0938 1.0936 1.0932 1.0927 I 6.0 1.1039 1.0784 1.0843 1.0883 1.0904 1.0916 1.0918 1.0921 1 6.2 1.1113 1.0759 1.0834 1.0889 1.0925 1.0950 1.0960 I.0970 1 6.4 1.1165 1.0712 1.0805 1.0874 1.0924 1.0963 1.0979 1.0998 1 6.6 1.1210 1.0660 1.0769 1.0853 1.0916 1.0968 1.0991 1.1019 1 6.8 1.1269 1.a624 1.0748 1.0846 I.0922 1.0988 1.I018 1.I054 Page 14 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 F I G W 5A (Cont'd)
BOC Part-Power W O C Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Height Part Power W(Z) with Correction Factor (excluding power ratio)
(feet) Hot Full 30% 40% 50% 60% 70% 75% 80%
Power Power Power Power Power Power Power Power 7.0 1.1326 I.0588 1.0726 1.0836 1.0925 1.1007 1.1043 1.1087 1 7.2 1.1370 1.0543 1.0694 1.0815 1.0917 1.1014 1.1057 1.1107 1- 7.4 1.1405 1.0490 1.0653 1.0788 1.0901 1.1012 1.1063 1.1118 1 7.6 1.1427 1.0428 1.0600 I.0749 1.0874 1.0997 I.I057 I.I 116 1, 7.8 1.1438 1.0357 1.0539 1.0700 1.0837 1.0972 1.I041 1.1105 1 8.0 1.1436 1.0272 1.0466 1.0635 1.0787 1.0935 1.I010 1.1083
- 1. 8.2 1.1420 1.0177 1.0382 1.0560 1.0725 1.0885 1.0967 1.1048 1 8.4 1.1391 1.0074 1.0289 1.0476 1.0653 1.0824 1.0912 1.1002 1 8.6 1.1350 0.9963 1.a187 1.0385 1.0570 1.0754 1.0848 1.0943 1 8.8 1.1279 0.9831 1.0063 1.0269 1.0463 1.0657 1.0757 1.0858 1 9.0 1.1261 0.9750 0.9989 1.0203 1.0406 I.0614 1.0720 I.0828 1 9.2 1.1353 0.9771 1.0019 1.0241 1.0455 1.0677 1.0791 1.0907 1 9.4 1.1515 0.9856 1.0112 1.0345 1.0571 1.0808 1.0930 1.1055 1 9.6 1.1665 0.9936 1.0196 1.0441 1.0679 1.0929 1.1059 1.1192 1 9.8 1.1843 1.0047 1.0313 1.0568 1.0819 1.1081 1.1219 1.1361 1, 10.0 1.2016 1.0161 1.0433 1.0697 1.0959 1.1234 1.1379 1.1530 1 10.2 1.2169 1.0267 1.0546 1.0815 1.1088 1.1374 1.1526 1.1685 1 10.4 1.OOOO 1.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO 1.OOOO 1.OOOO 1 10.6 1.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO 1 10.8 1.OOOO 1.OOOO 1.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO 1.OOOO I 11.0 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.oooo I.oooo 1 11.2 I.oooo 1.oooo 1.oooo 1.oooo 1.oooo 1.0000 I.oooo 1.oooo 1 11.4 1.OOOO 1.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO I.OOOO 1.OOOO 1 11.6 I.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO 1.OOOO I.OOOO 1.OOOO 1 11.8 1.OOOO 1.OOOO I.OOOO 1.OOOO I.OOOO 1.OOOO I.OOOO 1.OOOO 1 12.0 1.oooo 1.oooo 1.oooo 1.oooo 1.a000 1.oooo I.oooo I.oooo Page 15 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT ICYCLE 33 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE
-35.00 -30.00 -25.00 -20.00 -15.00 -10.00 -5.00 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 Delta I (%)
NOTE: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure 2 of ROD 1.2 for administrative limit.
Page 16 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT ICYCLE 33 TABLE I NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Technical Specification," February 1994 WCAP-14449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision I,October 1999 (cores containing 422V + fuel)
WCAP-10924-P-A, "Large Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addenda, December 1988 (cores not 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-10924-P-A, "LBLOCA Best Estimate Methodology: Model Description and Validation: Model Revisions," Volume 1, Addendum 4, August 1990 (cores not containing 422V + fuel)
WCAP-I 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 WCAP-10054-P-A, Addendum 2, Revision 1, Page 17 of 18
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 12 March 17, 2010 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 33 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS COLR Parameter NRC Approved Methodology Section 2.7 Nuclear Enthalpy Rise Hot Channel WCAP-9272-P-A, "Westinghouse Reload Factor ( F ~ ~ H ) Safety Evaluation Methodology," July 1985 2.8 Axial Flux Difference (AFD) WCAP-I 0216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control FQSurveillance Technical Specification," February 1994 2.9 Overtemperature AT Setpoint WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986 2.10 Overpower AT 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," April 1989, for those events Boiling (DNB) Limits analyzed using RTDP WCAP-14787-PI Rev. 2, 'Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 MWt-NSSS Power with Feedwater Venturis, or 1679 MWt-MSSS Power with LEFM on Feedwater Header)",
October 2002.
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 o'f 18