BW170043, Core Operating Limits Report, Cycle 20

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Core Operating Limits Report, Cycle 20
ML17125A220
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 05/05/2017
From: Marchionda-Palmer M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW170043
Download: ML17125A220 (17)
v • d • e


Text

May 5, 2017 BW170043 n

ti on U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Renewed Facility Operating License No. NPF-77 NRG Docket No. STN 50-457 Exelon Generation Company, LLC Braidwood Station 35100 South Route 53, U<ct~l1VH!O, IL 60407-9619 www.exeloncoro.com

Subject:

Core Operating Limits Report, Braidwood Unit 2 Cycle 20 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 20 in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 2 Cycle 20 COLR, Revision 1 O was implemented during Braidwood Unit 2 Refueling Outage 19 in support of Cycle 20 operation. Note that the revision number is based on a numbering convention that continues from the previous revision of the Unit 2 COLR, i.e.,

Braidwood Unit 2 Cycle 19, Revision 9.

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

Sincerely,

'i_ j

/.} I

/Jl/11\\JVJ l1 ivc~

Marri Marchionda-Palmer Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 20, Revision 1 O cc:

NRG Regional Administrator, Region Ill NRG Senior Resident Inspector - Braidwood Station NRG Project Manager, NRR - Braidwood and Byron Stations

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 20 EXELON TRACKING ID:

COLR BRAIDWOOD 2 REVISION 10

COLR BRAIDWOOD 2 Revision 10 Page 1of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 20 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (SOM)

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 (Fa(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN LiH)

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 (TRM) affected by this report are listed below:

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

COLR BRAIDWOOD 2 Revision 10 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 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 NRG-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.

inul Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 2 Revision 10 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 2.2 SHUTDOWN MARGIN (SOM)

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

2.2.1 The SOM shall be greater than or equal to 1.3% Ak/k (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 SOM limit for MODE 5 is:

2.2.2 SOM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.476 x 10-5 Ak/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 104 Ak/k/°F.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 Ak/k/°F.

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

COLR BRAIDWOOD 2 Revision 10 Page 4of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224)

(77%, 224) 220 200 180 c

~ 160 "C

.c -

§ 140 Ill Q.

CD -

!!!. 120 c

0

  • u; 0 100
a.

..:.:: c C'O al 80 "C

0 0::

60 40 20 r

r

/ /

/ /

~ANKB

,I/

I

,I

/

~/

1(0%, 162)

I L

/

/

IBANKC I

/

/'

/

/

/

/

IBANKD I

/

/ /

/

/

/

/

~fl(O%, 47) I

/

~/

1(30%.0)v T

(100%, 161) 0 0

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

COLR BRAIDWOOD 2 Revision 10 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 2.6 Heat Flux Hot Channel Factor (Fggu (LCO 3.2.1) 2.6.1 Total Peaking Factor:

1.1 1

0.9 0.8 N" 0.7

-a

u.

-g 0.6 cu E 0 0.5 z

N" Si2"' 0.4 0.3 0.2 0.1 0

pRTP FQ (Z) ~ _Q_xK(Z) for P ~ 0.5 0.5 pRTP FQ(Z) ~-Q-xK(Z) forP>0.5 p

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~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 I

I (o.o, 1.0) I 0

1 2

3 4

BOTTOM I

I (s.o, 1.0) I (12.0,0.924) I

~

-+-LOCA Limiting 5

6 7

Core Height (ft) 8 Envelope -

9 10 11 12 TOP

COLR BRAIDWOOD 2 Revision 10 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 2.6.2 W(Z) Values:

a) When the Power Distribution Monitoring System (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 that correspond to the NORMAL AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burnups of 150, 4000, 14000, and 20000 MWD/MTU. The Normal AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.
2) Table 2.6.2.b are the Expanded normal operation W(Z) values that correspond to the EXPANDED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The Expanded normal operation W(Z) values have been determined at burnups of 150, 4000, 14000, and 20000 MWD/MTU. The Expanded AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.

Table 2.6.2.c shows the Fe 0 (z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the Fw 0 (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, UFa. to be applied to the Heat Flux Hot Channel Factor F0(Z) shall be calculated by the following formula UFQ =Uqu*U, where:

Uqu = Base F0 measurement uncertainty= 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)

Ue = Engineering uncertainty factor= 1.03 2.6.4 PDMS Alarms:

F0(Z) Warning Setpoint = 2% F0(Z) Margin F0(Z) Alarm Setpoint = 0% F0(Z) Margin

COLR BRAIDWOOD 2 Revision 10 Page 7 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 Table 2.6.2.a W(Z) versus Core Height for Normal AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded perWCAP-10216)

Height 150 4000 14000 (feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.1646 1.2881 0.20 1.1559 1.2656 0.40 1.1505 1.2571 0.60 1.1437 1.2576 0.80 1.1385 1.2186 1.00 1.1317 1.2091 1.20 1.1216 1.2046 1.40 1.1174 1.2096 1.60 1.1294 1.1941 1.80 1.1335 1.1806 2.00 1.1253 1.1671 2.20 1.1161 1.1526 2.40 1.1079 1.1391 2.60 1.0993 1.1246 2.80 1.0915 1.1125 3.00 1.0839 1.1000 3.20 1.0863 1.0932 3.40 1.0932 1.0949 3.60 1.1009 1.0976 3.80 1.1076 1.0994 4.00 1.1135 1.1021 4.20 1.1194 1.1037 4.40 1.1235 1.1044 4.60 1.1266 1.1050 4.80 1.1295 1.1047 5.00 1.1306 1.1043 5.20 1.1300 1.1029 5.40 1.1293 1.1015 5.60 1.1279 1.0991 5.80 1.1359 1.0958 6.00 1.1426 1.0926 6.20 1.1483 1.1023 6.40 1.1530 1.1120 6.60 1.1557 1.1218 6.80 1.1575 1.1296 7.00 1.1582 1.1355 7.20 1.1689 1.1429 7.40 1.1784 1.1520 7.60 1.1861 1.1624 7.80 1.1934 1.1726 8.00 1.1989 1.1830 8.20 1.2027 1.1926 8.40 1.2059 1.2022 8.60 1.2074 1.2098 8.80 1.2128 1.2172 9.00 1.2188 1.2285 9.20 1.2230 1.2390 9.40 1.2346 1.2510 9.60 1.2377 1.2589 9.80 1.2353 1.2671 10.00 1.2294 1.2739 10.20 1.2315 1.2801 10.40 1.2333 1.2863 10.60 1.2292 1.2967 10.80 1.2347 1.3069 11.00 1.2480 1.3170 11.20 1.2590 1.3238 11.40 1.2565 1.3294 11.60 1.2586 1.3318 11.80 1.2589 1.3357 12.00 lcore tool 1.2635 1.3490 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 1.3035 1.2790 1.2692 1.2603 1.2405 1.2183 1.1960 1.1906 1.1834 1.1768 1.1687 1.1587 1.1504 1.1450 1.1407 1.1354 1.1322 1.1296 1.1257 1.1280 1.1318 1.1366 1.1402 1.1467 1.1532 1.1574 1.1609 1.1644 1.1650 1.1657 1.1803 1.1929 1.2026 1.2103 1.2151 1.2169 1.2148 1.2108 1.2048 1.1989 1.1929 1.1831 1.1753 1.1635 1.1545 1.1564 1.1614 1.1760 1.2180 1.2540 1.2860 1.3140 1.3380 1.3560 1.3710 1.3780 1.3220 1.3210 1.3038 1.2917 1.2844 20000 MWD/MTU 1.2530 1.2301 1.2192 1.2066 1.2007 1.1968 1.1894 1.1830 1.1730 1.1635 1.1526 1.1389 1.1305 1.1292 1.1289 1.1277 1.1255 1.1243 1.1413 1.1555 1.1695 1.1831 1.1939 1.2034 1.2117 1.2172 1.2214 1.2248 1.2435 1.2611 1.2747 1.2853 1.2929 1.2947 1.2955 1.2922 1.2832 1.2732 1.2592 1.2424 1.2246 1.2068 1.1890 1.1723 1.1688 1.1712 1.1840 1.2340 1.2830 1.3240 1.3600 1.3900 1.4160 1.4330 1.4500 1.4600 1.4530 1.4199 1.3969 1.3848 1.3806

COLR BRAIDWOOD 2 Revision 10 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 Table 2.6.2.b W(Z) versus Core Height for Expanded AFD Acceptable Operation Limits In Figure 2.8.1.b (Top and Bottom 8% Excluded oerWCAP-10216}

Height 150 4000 14000 (feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 <core bottom\\

1.2837 1.4294 1.4541 0.20 1.2717 1.4007 1.4244 0.40 1.2648 1.3900 1.4128 0.60 1.2570 1.3846 1.4013 0.80 1.2479 1.3453 1.3773 1.00 1.2384 1.3323 1.3512 1.20 1.2239 1.3192 1.3175 1.40 1.2173 1.3202 1.3011 1.60 1.2262 1.2995 1.2856 1.80 1.2271 1.2802 1.2729 2.00 1.2148 1.2598 1.2584 2.20

1. 1990 1.2365 1.2418 2.40 1.1857 1.2154 1.2263 2.60 1.1700 1.1940 1.2124 2.80 1.1600 1.1757 1.2063 3.00 1.1531 1.1694 1.1993 3.20 1.1489 1.1639 1.1897 3.40 1.1459 1.1591 1.1817 3.60 1.1419 1.1524 1.1798 3.80
1. 1423 1.1469 1.1794 4.00 1.1462 1.1394 1.1779 4.20 1.1499 1.1314 1.1745 4.40 1.1517 1.1229 1.1705 4.60 1.1524 1.1132 1.1646 4.80 1.1530 1.1106 1.1582 5.00 1.1517 1.1088 1.1574 5.20 1.1483 1.1061 1.1609 5.40 1.1449 1.1032 1.1644 5.60
1. 1395 1.0995 1.1650 5.80 1.1359 1.0958 1.1657 6.00 1.1426 1.0926 1.1803 6.20 1.1483 1.1023 1.1929 6.40 1.1530 1.1120 1.2026 6.60 1.1557 1.1218 1.2103 6.80 1.1575 1.1296 1.2151 7.00 1.1582 1.1355 1.2169 7.20 1.1689 1.1429 1.2148 7.40 1.1784 1.1520 1.2108 7.60 1.1861 1.1624 1.2048 7.80 1.1934 1.1726 1.1989 8.00 1.1989 1.1830 1.1929 8.20 1.2027 1.1926 1.1831 8.40 1.2059 1.2022 1.1753 8.60 1.2074 1.2098 1.1635 8.80 1.2128 1.2172 1.1545 9.00 1.2188 1.2285 1.1564 9.20 1.2230 1.2390 1.1614 9.40 1.2346 1.2510 1.1760 9.60 1.2377 1.2589 1.2180 9.80 1.2353 1.2671 1.2540 10.00 1.2294 1.2739 1.2860 10.20 1.2315 1.2801 1.3140 10.40 1.2333 1.2863 1.3380 10.60 1.2292 1.2967 1.3560 10.80 1.2347 1.3069 1.3710 11.00 1.2480 1.3170 1.3780 11.20 1.2590 1.3238 1.3220 11.40 1.2565 1.3294 1.3210 11.60 1.2586 1.3318 1.3038 11.80 1.2589 1.3357 1.2917 12.00 {core tool 1.2635 1.3490 1.2844 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 20000 MWD/MTU 1.3485 1.3397 1.3382 1.3367 1.3319 1.3258 1.3153 1.3064 1.2929 1.2803 1.2666 1.2486 1.2321 1.2112 1.1929 1.1763 1.1783 1.1837 1.1881 1.1917 1.1941 1.1943 1.1939 1.2034 1.2117 1.2172 1.2214 1.2248 1.2435 1.2611 1.2747 1.2853 1.2929 1.2947 1.2955 1.2922 1.2832 1.2732 1.2592 1.2424 1.2246 1.2068 1.1890 1.1723 1.1688 1.1712 1.1840 1.2340 1.2830 1.3240 1.3600 1.3900 1.4160 1.4330 1.4500 1.4600 1.4530 1.4199 1.3969 1.3848 1.3806

Notes:

COLR BRAIDWOOD 2 Revision 10 Page 9of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penal~ Factor (MWD/MTU)

F ;o(Z) 326 1.0200 1203 1.0378 1379 1.0399 1554 1.0377 1730 1.0346 1905 1.0311 2081 1.0272 2256 1.0233 2432 1.0200 8224 1.0209 8850 1.0277 9453 1.0285 10050 1.0285 11400 1.0210 11559 1.0200 12964 1.0205 13139 1.0210 14017 1.0229 14543 1.0203 14719 1.0200 Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

COLR BRAIDWOOD 2 Revision 10 Page 10 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20

2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN@ (LCO 3.2.2) 2.7.1 FN aH ~ F~~P[1.0 + PFaH(1.0 - P)]

where: P =the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F~~P = 1.70 PFaH = 0.3

2.7.2 Uncertainty

The uncertainty, UFaH. to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN aH shall be calculated by the following formula:

where:

UF&fm = Base FN aH measurement uncertainty = 1.04 when PDMS is inoperable (UFaHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN aH Warning Setpoint = 2% FN aH Margin FN aH Alarm Setpoint = 0% FN 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 Normal AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.a. Prior to changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.

b) Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.b.

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 ~ 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsd 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

COLR BRAIDWOOD 2 Revision 10 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 Figure 2.8.1.a:

120

-50 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference limits with PDMS Inoperable I (-10, 100) I I

I I

Una:cceptab e I

I 1

u_~,ccept 'ble Operati n 0: eration

-40

-30

-20

-10 0

10 20 30 40 AXIAL FLUX DIFFERENCE (%)

so

COLR BRAIDWOOD 2 Revision 10 Page 12of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 a:

w

~

0 Q.,

ct

?

a:

w

c Q

w ti:

a: -

0

~

Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits with PDMS Inoperable 120 T"--"~~~,~,,~;-,~~-,,,_7 __

,;*--*';~-~-,,-,

_,,,,,,,,,,_,~-*,~--*~~,,-~,~

I (-ls, 100) 1

! I (+10, 1ooi 1 100 ,,~,_,,,,,,,,,,,.,,..,.,,,,,,,.;,.. ~._,,,.,,,~,,.;,.,,,.. r-"""\\""'----""'l;;"""""'!,,,,,,,,,....,,,... ! '"'.....,,..,,,,,,,,,,,,,,,,c 80 I

Accettable 60 Ope 1ation 40 20

-50

-40

-30

-20

-10 0

10 20 30 40 so AXIAL FLUX DIFFERENCE (%)

COLR BRAIDWOOD 2 Revision 10 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UN1T 2 CYCLE 20 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I psi.

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 588.0 °F.

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

2.10.6 The measured reactor vessel AT lead/lag time constant.. 1 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel AT lead/lag time constant *z shall be equal to 3 sec.

2.10.8 The measured reactor vessel AT 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 lead/lag time constant *s shall be equal to 4 sec.

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

2.10.12 The f1 (Al} "positive" breakpoint shall be +10% Al.

2.10.13 The f1 (Al} "negative" breakpoint shall be-18% Al.

2.10.14 The f1 (Al} "positive" slope shall be +3.47% I% Al.

2.10.15 The f1 (Al} "negative" slope shall be -2.61 % I% Al.

COLR BRAIDWOOD 2 Revision 10 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint Ki shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02 / °F for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tavg.

2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 0.00245 / °F when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 0 I °F when T::;; T".

2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 °F 2.11.7 The measured reactor vessel AT lead/lag time constant.. 1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant.. 2 shall be equal to 3 sec.

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

2.11.10 The measured reactor vessel average temperature lag time constant 'ts 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 f2 (Al} "positive" breakpoint shall be 0 for all Al.

2.11.13 The f2 (Al) "negative" breakpoint shall be 0 for all Al.

2.11.14 The f2 (Al} "positive" slope shall be 0 for all Al.

2.11.15 The f2 (Al} "negative" slope shall be 0 for all Al.

COLR BRAIDWOOD 2 Revision 10 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 20 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 (Tavg) shall be less than or equal to 593.1 °F.

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 applicable value given in the Table below (LCO 3.9.1 ). The reported "prior to initial criticality" 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 applicable values given in the Table below.

COLR Boron Concentration Section Conditions (ppm) 2.13.1 a) prior to initial criticality 1664 b) for cycle burn ups ~ 0 MWD/MTU 1778 and < 16000 MWD/MTU c) for cycle burnups ~ 16,000 MWD/MTU 1393 2.13.2 a) prior to initial criticality 1720 b) for cycle burn ups ~ 0 MWD/MTU and <

1958 16000 MWD/MTU c) for cycle burnups ~ 16000 MWD/MTU 1502

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