ML12128A361

Core Operating Limits Report, Cycle 17

ML12128A361
Person / Time
Site:	Braidwood
Issue date:	05/07/2012
From:	Enright D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW120046
Download: ML12128A361 (17)

Text

May 7,2012 BW120046 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 17 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 17, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR}." Braidwood Unit 1 Cycle 17 COLR, Revision 9 was implemented during Braidwood Unit 1 Refueling Outage 16 in support of Cycle 17 operation. Note that Revision 9 is the original version of the Braidwood Unit 1 Cycle 17 COLR implemented in support of Cycle 17 operation. The revision number is based on a numbering convention that continues from the previous revision of the Unit 1 COLR, Le., Braidwood Unit 1 Cycle 16 COLR, Revision 8.

If you have any questions regarding this matter, please contact Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-2800.

Sincerely, Daniel J. Enright Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 17, Revision 9 cc: NRC Regional Administrator, Region '"

NRC Senior Resident Inspector - Braidwood Station

TOOl NF1200069 Revision 0 Page 7 of 50 CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 1 CYCLE 17 EXELON TRACKING 10:

COLR BRAIDWOOD 1 REVISION 9

TODI NF1200069 Revision 0 Page 8 of 50 COLR BRAIDWOOD 1 Revision 9 Page 1 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 17 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specifications affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

N LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F t\H)

LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below:

TRM TLCO 3.1.b Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1.h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff?: 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)

TOOl NF1200069 Revision 0 Page 9 of 50 COLR BRAIDWOOD 1 Revision 9 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 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 are applicable for the entire cycle unless otherwise identified. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.

2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1) 2.1.1 In MODES 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.

680 . - - - - - - - , r - - - - - ' - - - , - - - - . , - - - - , - - - - . - - - - - ,

660 +-----.;;~I::::----1----+----;----+-----I

-La..

c:n

~

........., 6 40 -t-----+----.::~.,,_---t_---+_--"""~-+---__I

~

J e

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620 -t--...:::...,.."..-+_---~;:::"..,::::__-+_---+_---+_""'""".,.....___.JI c:n e

<1,)

~

600 +----r----+----t-----.,;:::......:::f----;---:::::..-.;::::--;

o .2 .4 .6 .8 1.2 Fradion of Nominal Power Figure 2.1.1: Reactor Core Limits

TOOl NF1200069 Revision 0 Page 10 of 50 COLR BRAIDWOOD 1 Revision 9 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 2.2 SHUTDOWN MARGIN (SDM)

The SDM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SDM shall be greater than or equal to 1.3% L\klk (lCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TlCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).

The SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% L\klk (lCO 3.1.1, lCO 3.3.9; TRM TlCOs 3.1.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTG) (lCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOUARO/HZP-MTC upper limit shall be +1.830 x 10'5 L\klkloF.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10'4 L\klkloF.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10'4 L\klkloF.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10'4 L\klkloF.

where: BOl stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOl stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (lCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.

2.5 Control Bank Insertion Limits (lCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.5.4 Each control bank not fUlly withdrawn from the core shall be operated with the following overlap limits as a function of park position:

Park Position (step) Overlap Limit (step) 226 111 227 112 228 113 229 114

TOOl NF1200069 Revision 0 Page 11 of 50 COLR BRAIDWOOD 1 Revision 9 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%,224) (77%,224) 220 -t=:::::r:=:::::r:=7-+'::::=r:::::::r::::::::r:::::=+~~::::=r:::::::r 200 1 /V

+----+------.~--+--_+_-__+I--+------F-+---+--+----i

/V I "J/[BANK B I I ~V I

'2 180 i - - -/+------+---+--+----+-- - - / + - + - -~I-------I

~

3= V I I II--+I--+IL-~~i--+---+:

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160 lr-(O-o/t-o,-1...1..

V I

--+1 --+/-----A (100%,161) i 140 +---+--+---+-/--Jl~r;::IB;-;A:-'N;;K~CIIf--+---+--+-/-~L---l S I

!!!. 120 +---+--+---+,.-...-+---+--+--_+1--~'--_+-____i t 100 t---t--+17~/-t1--+' V

--+1__t-_-t~~/=:+/-:V=====.-t-_---i V IBANKO I

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~I(O%, 47) I I /

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20 II I

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o 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

TOOl NF1200069 Revision 0 Page 12 of 50 COLR BRAIDWOOD 1 Revision 9 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 2.6 Heat Flux Hot Channel Factor (Fa!lll (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FQ (Z) ::;; xK(Z) for P ::;; 0.5 0.5 F RTP FQ(Z) ::;;-Q-xK(Z) forP>0.5 P

where: P = the ratio ofTHERMAL POWER to RATED THERMAL POWER F6'TP = 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z)

• Normalized FQ(Z) as a Function of Core Height 1.1 (0.0 1.0) (6.0 1.0)

(12. ,0.924) 0.9 -

0.8 E!a 0.7 u.

"Cl CIl 0.6

.~

Ri E 0.5 0

z

~

~

.....LOCA Limiting 0.4 Envelope 0.3 0.2 0.1 o

o 1 2 3 4 5 6 7 8 9 10 11 12 BOnOM Core Height (tt) TOP

TOOl NF1200069 Revision 0 Page 13 of 50 COLR BRAIDWOOD 1 Revision 9 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 2.6.2 W(Z) Values:

a) When PDMS is OPERABLE, W(Z) = 1.00000 for all axial points.

b) When PDMS is inoperable, W(Z) is provided as:

1) Table 2.6.2.a are the normal operation W(Z) values for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burn ups of 150, 6000,14000, and 20000 MWD/MTU.

2) The EOl-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups ?: 18000 MWD/MTU. The EOl-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The EOl-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOl-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.

Table 2.6.2.c shows the Feo(z) penalty factors that are greater than 2% per 31 Effective W

Full Power Days (EFPD). These values shall be used to increase the F o(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.c.

2.6.3 Uncertainty

The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula where:

Uqu = Base Fo measurement uncertainty = 1.05 when PDMS is inoperable (U qu is defined by PDMS when OPERABLE.)

Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

Fo(Z) Warning Setpoint = 2% Fo(Z) Margin Fo(Z) Alarm Setpoint = 0% Fo(Z) Margin

TOOl NF1200069 Revision 0 Page 14 of 50 COLR BRAIDWOOD 1 Revision 9 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.a c==r (Top and Bottom S% Excluded per WCAP-10216)

,00 (core bottom) 020 MWDfMTU

'00 1.3982 1.3782

=f= - MWDfMTU 1,5005 1.4634 14000 MWDfMTU 1.3544 1.3346 20000 MWDfMTU 1.3541 1.3350 0.40 1.3683 1.4488 1.3257 1.3268 060 1.3573 1,4352 1.3052 1.3121 0.80 1.3454 1.4050 1.3117 1.3266 1,00 1.3334 1.3934 1.3077 1.3170 120 1.3175 1.3819 12772 12997 1.40 12955 1.3634 12694 12897 1.60 12766 1.3390 1.2484 12716 180 12607 1.3166 1.240F+ 1.2599 2.00 12447 12941 12346 12471

~

220 12679 1,2246 12307 2.40 12464 1.2166 1.2152 2.60 1.2025 1.2221 1.2056 1.1960 2.80 1.1931 1.1998 1.1957 1,1777 3.00 1.1851 1.1826 1.1847 1.1621 320 1.1797 1.1773 1,1732 11560 3.40 1.1756 1.1723 1.1645 1.1511 3.60 1.1691 1.1658 11540 1.1542 3.80 1.1632 1.1597 1.1449 1.1584 4.D0 1.1571 1.1532 1.1444 1.1620 420 11495 1.1441 1.1416 1.1674 4.40 1.1416 1.1356 1.1390 1,1782 4.60 1.1321 1.1255 1.1349 1.1882 4.80 1.1235 1.1159 1.1400 1.1959 5.00 1.1138 1.1074 1.1446 1.2017 5.20 11026 1.1053 1.1471 1,2049 5.40 1,0912 1.1024 1.1487 1.2083 5.60 1.0907 1,0989 1.1501 1.2221 5.80 1,0995 1.0965 1.1496 12405

~600 1.1074 1,0951 1.1645 1,2560 620 1.1153 1.1029 1,1791 12676 6.40 1.1213 1.1106 1.1907 12772 6.60 1.1263 1.1193 1.1994 1.2810 6.80 1.1293 1.1261 12062 1.2837 700 1.1331 1.1328 12109 12835 720 1.1360 1.1391 1,2128 1,2774 7.40 1.1372 1.1474 1,2127 1.2704 7.60 1.1355 1.1553 1.2087 12584 7.80 1.1360 1.1631 12038 12455 8.00 1.1384 1.1694 1.1978 12306 820 1.1426 1,1747 1.1899 1.2109 8.40 1.1488 1,1785 1.1831 1.1994 8.60 1.1484 1.1803 1.1802 1.1953 8.80 1.1540 1.1831 1.1793 1.1932 9.00 11597 1.1869 1.1770 1.1891 920 1.1651 1.1945 1.1727 1.1865 9.40 1.1689 1.1987 1.1771 12348 9.60 11709 12034 1.1857 12805 9.80 1,1713 1.2086 1.2183 1.3230 10.00 1.1738 1.2171 1.2469 1.3616 1020 1.1791 1,2263 1,2746 1.3973 10.40 1.1859 1,2320 1.2963 1.4290 10.60 1.1942 1.2353 1.3161 1.4537 10.80 1.1986 1.2408 1.3308 1.4715 11.00 1.2054 1.2436 1.3336 1.4834 1120 1,2176 12657 1.3415 1.4823 11.40 1.2234 12699 1.3344 1.4801 11,60 1.2251 1.2798 1.3253 1.4621 11.80 12277 1.2848 1.3133 1.4501 12.00 (core top) 1.2369 12961 1.3040 1,4438 Note: W(Z) values at 20000 MNDfMrU may be applied to cycle bumups greater than 20000 MWDfMrU to prevent W(Z) function extrapolation

TODI NF1200069 Revision 0 Page 15 of 50 COLR BRAIDWOOD 1 Revision 9 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 Table 2.6.2.b EOL-only W{Zl versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Botlom 8% Excluded per WCAp*102161 Height 18000 20000 23896 (feell MWD/MTU MWD/MTU MWD/MTU 0.00 (core botlom) 1.1937 1.1989 1.1989 0.20 1.1858 1.1893 1.1893 0.40 1.1831 1.1880 1.1880 0.80 1.1815 1.1838 1.1838 0.80 1.1912 1.1958 1.1958 1.00 1.1910 1.1909 1.1909 1.20 1.1739 1.1772 1.1772 1.40 1.1682 1.1697 1.1697 1.60 1.1582 1.1559 1.1559 1.80 1.1509 1.1469 1.1469 2.00 1.1430 1.1369 1.1369 2.20 1.1323 1.1242 1.1242 2AO 1.1220 1.1120 1.1120 2.60 1.1157 1.1063 1.1083 2.80 1.1114 1.1083 1.1083 3.00 1.1074 1.1073 1.1073 3.20 1.1053 1.1054 1.1054 3AO 1.1079 1.1105 1.1105 3.80 1.1153 1.1251 1.1251 3.80 1.1250 1.1378 1.1378 4.00 1.1344 1.1494 1.1494 4.20 1.1425 1.1592 1.1592 4AO 1.1538 1.1718 1.1718 4.60 1.1639 1.1834 1.1834 4.80 1.1723 1.1929 1.1929 5.00 1.1791 1.2004 1.2004 5.20 1.1831 1.2049 1.2049 5AO 1.1861 1.2083 1.2083 5.60 1.1949 1.2221 1.=1 5.80 1.2053 1.2405 1.2405 6.00 1.=0 1.2580 1.2580 6.20 1.2354 1.2676 1.2676 6AO 1.2462 1.2772 1.2772 6.60 1.2521 1.2810 1.2810 I 6.80 1.2565 1.2837 1.2837 7.00 1.2583 1.2835 1.2835 I 7.20 1.2553 1.2774 1.2774 7AO 1.2506 1.2704 1.2704 7.80 1.2410 1.2584 1.2584 7.80 1.2305 1.2455 1.2455 I 8.00 1.2184 1.2306 1.2306 I 8.20 1.2028 1.2109 1.2109 8AO 1.1925 1.1994 1.1994 8.80 1.1885 1.1953 1.1953 8.80 1.1866 1.1932 1.1932 9.00 1.1828 1.1891 1.1891 9.20 1.1785 1.1865 1.1865 9AO 1.2078 1.2348 1.2348 9.60 1.2376 1.2805 1.2805 9.80 1.2780 1.3230 1.3230 10.00 1.3139 1.3616 1.3616 10.20 1.3476 1.3973 1.3973 10AO 1.3762 1A290 1A290 10.60 1A002 1A537 1A537 10.80 1A174 1A715 1A715 11.00 1A253 1A834 1A834 11.20 1A269 1A823 1A823 11AO 1A217 1A801 1A801 11.60 1A059 1A621 1A621 11.80 1.3925 1A501 1A501 12.00 (core top) 1.3833 1.4438 1A438 Note. W(ZJ values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(ZJ function extrapolation

TOOl NF1200069 Revision 0 Page 16 of 50 COLR BRAIDWOOD 1 Revision 9 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPO Cycle Bumup Penalty Factor (MWD/MTU) FCQ(z) o 1.0393 323 1.0416 496 1.0431 668 1.0432 1014 1.0400 1360 1.0272 1705 1.0200 14839 1.0200 15358 1.0252 15531 1.0260 15876 1.0253 17259 1.0285 17604 1.0283 17950 1.0283 18641 1.0280 19160 1.0265 19333 1.0260 20888 1.0213 21061 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All cycle bumups outside the range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

TOOl NF1200069 Revision 0 Page 17 of 50 COLR BRAIDWOOD 1 Revision 9 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 N

2.7 Nuclear Enthalpy Rise Hot Channel Factor (F £lljl (LCO 3.2.2) 2.7.1 F N

AH ::; F~~P[1.0 + PF AH (1.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~~P = 1.70 PF AH =0.3

2.7.2 Uncertainty

The uncertainty, UFAH , to be applied to the Nuclear Enthalpy Rise Hot Channel Factor N

F AH shall be calculated by the following formula:

where:

UFiJHm =Base F N AH =

measurement uncertainty 1.04 when PDMS is inoperable (U FAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

N N F AH Warning Setpoint = 2% F AH Margin N N F ilH Alarm Setpoint = 0% F AH Margin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.

b) Figure 2.8.1.b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1.b, confirm that the plant is within the specified AFD envelope.

2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.

2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPsL ~ 1.539 The Axial Power Shape Limiting DNBR (DNBRAPsLl is applicable with THERMAL POWER

~ 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin

TOOl NF1200069 Revision 0 Page 18 of 50 COLR BRAIDWOOD 1 Revision 9 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 Figure 2.8.1.a:

Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)

Flux Difference Limits with PDMS Inoperable 120 I

<-15[100)1 I

(+1 0, ~ 00) I I

100 i

\

I I i I Ix:

w unacc~Ptablf I Una~cepta lie

~

0 80 Ope ation / I 0 ~eratio 1 A~cePta~le V

a.

...I

E Ix:

w i c peratic'n I

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60

r:

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/ I i

(+~5, 5( I)

...~

(-3 5,50' I 40 I

0~

0 I

i I

20 o I I

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

TOOl NF1200069 Revision 0 Page 19 of 50 COLR BRAIDWOOD 1 Revision 9 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 Figure 2.8.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup ~ 18000 MWD/MTU)

Axial Flux Difference Limits with PDMS Inoperable 100 a:;

W

~

0 Q. 80

...I

<< :aE 0::

w 60 J:

l-e w

~.... 40 0

0~

20 o +----+--+---+--+-----i---+---+----i---+------.j

-50 -40 -30 -20 -10 o 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

TOOl NF1200069 Revision 0 Page 20 of 50 COLR BRAIDWOOD 1 Revision 9 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature 6.T Setpoint Parameter Values 2.10.1 The Overtemperature 6. T reactor trip setpoint K 1 shall be equal to 1.325.

2.10.2 The Overtemperature 6.T reactor trip setpoint T avg coefficient K 2 shall be equal to 0.0297/ of.

2.10.3 The Overtemperature 6.T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181/ psi.

2.10.4 The nominal T avg at RTP (indicated) T' shall be less than or equal to 588.0 of.

2.10.5 The nominal RCS operating pressure (indicated) P' shall be equal to 2235 psig.

2.10.6 The measured reactor vessel 6. T lead/lag time constant '1 shall be equal to 8 sec.

2.10.7 The measured reactor vessel 6. T lead/lag time constant '2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel 6.T lag time constant '3 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant '4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature leadllag time constant '5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant '6 shall be less than or equal to 2 sec.

2.10.12 The f 1 (6.1) "positive" breakpoint shall be +10% 6.1.

2.10.13 The f 1 (6.1) "negative" breakpoint shall be -18% 6.1.

2.10.14 The f 1 (6.1) "positive" slope shall be +3.47% / % 6.1.

2.10.15 The f 1 (6.1) "negative" slope shall be -2.61% / % 6.1.

TOOl NF1200069 Revision 0 Page 21 of 50 COLR BRAIDWOOD 1 Revision 9 Page 14 of15 CORE OPERATING LlMITS REPORT (COLR) for BRAIDWOOD IJNIT 1 CYCLE 17 2.11 Reactor Trip System IRTS) Instrumentation (LeO 3.3.1) - Overpower ~T Setpoint Parameter Values 2.11.1 The Overpower ~ T reactor trip setpoint ~ shall be equal to 1.072.

2.11.2 The Overpower ~T reactor trip setpoint T avg rate/lag coefficient Ks shall be equal to 0.02/ OF for increasing T avg .

2.11.3 The Overpower ~ T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0/ OF for decreasing T avg .

2.11.4 The Overpower ~T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245/ OF when T > T".

2.11.5 The Overpower ~T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / OF when T :S; T".

2.11.6 The nominal T avg at RTP (indicated) T" shall be less than or equal to 588.0 OF 2.11.7 The measured reactor vessel ~T lead/lag time constant '1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel ~ T lead/lag time constant '2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel ~T lag time constant '3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant '6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant '7 shall be equal to 10 sec.

2.11.12 The f 2 (~I) "positive" breakpoint shall be 0 for all ~I.

2.11.13 The f 2 (~I) "negative" breakpoint shall be 0 for all ~1.

2.11.14 The f 2 (~I) "positive" slope shall be 0 for all ~I.

2.11.15 The f 2 (~I) "negative" slope shall be 0 for all ~1.

TOOl NF1200069 Revision 0 Page 22 of 50 COLR BRAIDWOOD 1 Revision 9 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 17 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.

2.12.2 The RCS average temperature (T avg ) shall be less than or equal to 593.1 of.

2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the value given in the Table below (LCO 3.9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle.

2.13.2 To maintain keff:": 0.987 with all shutdown and control rods fUlly withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the values given in the Table below.

COLR Conditions Boron Concentration Section (ppm) 2.13.2 a) prior to initial criticality 1793 2.13.2 b) all other times in life