ML14045A195

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Core Operating Limits Report, Braidwood Unit 1 Cycle 18 and Braidwood Unit 2 Cycle 17 for Mur Operation
ML14045A195
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 02/14/2014
From: Kanavos M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW140002
Download: ML14045A195 (34)
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Text

February 14, 2014 BW140002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 18 and Braidwood Unit 2 Cycle 17 for MUR operation

References:

(1) Letter from Craig Lambert (Exelon Generation Company, LLC) to u. S.

NRC, "Request for License amendment Regarding Measurement Uncertainty Recapture (MUR) Power Uprate", dated June 23, 2011 (2) Letter from J. S. Wiebe (U. S. NRC) to M. J. Pacilio, "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 -Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate (TAC Nos. MF2418, MF2419, MF2420, and MF2421)", dated February 7,2014 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 18 and Braidwood Unit 2 Cycle 17, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)", to support Measurement Uncertainty Recapture (MUR) operation.

Braidwood Unit 1 Cycle 18 COLR, Revision 11 was implemented to support MUR during Braidwood Unit 1 Cycle 18 operation. Braidwood Unit 2 Cycle 17 COLR, Revision 7 was implemented to support MUR during Braidwood Unit 2 Cycle 17 operation. Note: The revision number is based on a numbering convention that continues from previous ro",e,r*., of the COLR.

If you have regarding this matter, please Phil Regulatory Assurance Manager, at (815) 7-2800.

Mark Kanavos

February 14, 2014 BW140002 Page 2 of 2

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 18, Revision 11 Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 17, Revision 7 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 1 CYCLE 18 EXELON TRACKING 10:

COLR BRAIDWOOD 1 REVISION 11

COLR BRAIDWOOD I Revision II Page I of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 18 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 (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>>

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NAH)

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 (BOPS)

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 Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources -

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

COLR BRAIDWOOD 1 Revision 11 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 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.

1-t71 psia 1250 psia

~-..

2000 pSia Figure 2.1.1: Reactor Core limits

COLR BRAIDWOOD 1 Revision II Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 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% Aklk (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% Aklk (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 BOLIARO/HZP-MTC upper limit shall be +1.735 xi 0-5 Aklkl°F.

2.3.2 The EOLIARO/HFP-MTC lower limit shall be -4.6 x 10-4 AklkloF.

2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 AklkloF.

2.3.4 The EOLIARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 AklkloF.

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 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 withdrawn from the core shall be nn""r""t<~rI with the r"/~~r!"",n limits as a function of Park Position (step) Overlap Limit (step) 227 112 228 113 229 114

COLR BRAIDWOOD 1 Revision II Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 Figure 2.5.1:

Control Bank Insertion limits Versus Percent Rated Thermal Power 224 (27%,224) (77%,224)

I' I' 220

/

V /

V 200

~

~ANKB I

~

V 180

'2

~

... 160

/ V (100%, 161)

I L /

III (0%, 162)

"C

.c 3: 140 IBANK C I

~

1/1 Q.

~ 120 / ,/

t::

0

l

'iii 0 100

/' /

Il.

.lI:: V I V IBANKD I

~ /

t::

III III ,

80 "C

0 a:: / I I

II /

60 / I I

/

L 40 t', (0%,47) I L V I 20 I /

I /(30%,0)V o

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

COLR BRAIDWOOD 1 Revision 11 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 2.6 Heat Flux Hot Channel Factor (Fggu (LCO 3.2.1) 2.6.1 Total Peaking Factor:

RTP FQ FQ(Z) 5 --xK(Z) for P 50.5 0.5 FR.T!'

FQ(Z) 5 -(-)-xK(Z) for P > 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 1.1 (O.C 1.0) (6.0 1.0) 1 (12.( 0.924) 0.9 0.8 NO.7 LL a

-g 0.6 iii E

o 0.5 z

.......... lOCA limiting

~ 0.4 Envelope I--

0.3 0.2 0.1 o

o 2345678 9 o 1 12

COLR BRAIDWOOD 1 Revision II Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 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 for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.B.1 ,a. The normal operation W(Z) values have been determined at burnups 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 2 18000 MWD/MTU. The EOl-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2,B.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 Full Power Days (EFPD). These values shall be used to increase the FWo(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 Fa 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:

Warning Setpoint =2%

Alarm Setpoint =

COLR BRAIDWOOD I Revision I I Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.8 (Top and Bottom 8% Excluded perWCAP-10216)

Height 150 6000 14000 20000 (feet) MWDlMTU MWDlMTU MWDlMTU MWD/MTU 0<00 (core bottom) 1.2611 1<3994 1.4556 1<3930 0.20 1.2416 1<3664 14242 1<3769 040 12308 1<3529 1A157 1<3643 0<60 12206 1<3413 1<3999 1<3535 0<80 1.2122 1<3127 1.3759 1<3391 1<00 12039 1<2794 1<3601 L3321 1.20 1<1934 1.2625 1<3372 1.3222 lAO 1<1912 1.2488 1<3182 1.3123 1<60 U96D 1.2313 1<3003 1.2995 1<80 1<2039 12159 12844 12876 2<00 11920 11985 1.2703 1.2747 2<20 U781 11857 12586 1.2568 2AO U652 11780 1<2459 1.2410 2<60 U530 1<1693 1.2321 1.2221 2<80 1<1472 11631 1.2201 1.2043 3<00 U406 U5B7 12072 11879 3<20 11381 11550 1<1935 11862 3AO 1<1391 1<1513 11905 1<1845 3BO 11438 1<1486 U871 U816 3<BO 11477 1<1411 11832 U809 4<00 1<1506 11354 U788 U792 420 1<1523 11281 11724 11762 440 U54D 1<1207 U66D 1<1806 4<60 U538 11117 11579 U902 4<80 U534 1<1037 11494 1<1970 5<00 U521 1<0989 1<1395 1.2025 5.20 11497 U049 U343 1.2065 SAO 1<1454 1.1109 1<1367 1.2090 5BO U499 U162 11373 1.2085 5BO 1.1549 U205 11369 12192 6.00 1.1621 11250 11458 1.2328 6.20 1.1776 U276 U586 1.2445 6.40 I U924 1.1311 U662 12532 6.60 I 1<2043 U339 U741 1.2579 6.80 1.2152 1.1*443 U793 1.2608 7<00 1.2252 1.1546 1.1625 1.2597 7.20 U324 1.1635 UB40 1.2546 7.40 1.2389 U705 11830 1.2486 7.60 1.2426 U751 U780 12367 7.80 1.2463 1.1772 U733 1.2248 8.00 1.2492 U8S0 11678 1.2109 8.20 12473 1.1910 UB11 1.1922 8.40 12433 1.1990 U564 U745 6<60 I 12399 1.2050 1.1554 1.1578 8.80 12344 1.2230 11545 1.1449 9<00 1.2271 1.2430 11527 1~~20 9.20 1.2188 1.2640 US08 1.1528 R40 1.2155 1.2820 11490 11920 9.60 1.2165 12980 U580 1.2370 980 1.2260 U140 11920 1.2750 10.00 1.2350 1.3280 1.2210 1.3090 10.20 U430 1.3370 1.2540 1.3400 lOAD 1.2500 1.3380 1.2750 1.3684 10.60 1.2690 D320 1.2960 1.3981 10<80 1.2710 1.3232 D050 1.4189 11.00 1.2680 1.3162 1.3060 1.4327 11.20 1.2730 1.3305 1.2820 14097 11.40 11.60 11.80 12<00 (core top) 1.2770 1.2800 1.2840 1.2920 ......

1.3523 1.3616 1.3721 1.3923 f=

L 1.2880 1.2700 12614 1.2522 1.4056 1.3896 1.3805 1.3773

COLR BRAIDWOOD 1 Revision II Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 Table 2.S.2.b EOL-only W{Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.B.l.b (Top and Boltom 8% Excluded perWCAP-l0216)

Height 18000 20000 25486 (leet) MWDIMTU MWD/MTU MWDlMTU 0.00 (core bottom) 1.2938 1.2470 1.2470 0.20 1.2747 1.2337 1.2337 0040 1.2661 1.2232 1.2232 0.60 1.2585 1.2208 1.2208 0.80 1.2481 1.2171 1.2171 1.00 1.2415 1.2124 1.2124 1.20 1.2282 1.2050 1.2050 1.40 1.2172 1.1975 1.1975 1.60 1.2097 1.1878 1.1878 1.80 1.2025 1.1784 1.1784 2.00 1.1941 1.1680 1.1680 2.20 1.1821 1.1538 1.1538 2040 1.1715 1.1425 1.1425 2.60 1.1596 1.1321 1.1321 2.80 1.1517 1.1272 1.1272 3.00 1.1451 1.1253 1.1253 3.20 1.1396 1.1262 1.1262 3.40 1.1370 1.1269 1.1269 3.60 1.1405 1.1332 1.1332 3.80 1.1453 1.1436 1.1436 4.00 1.1524 1.1577 1.1577 4.20 1.1574 1.1696 1.1696 4AO 1.1617 1.1806 1.1806 4.60 1.1643 1.1902 1.1902 4.80 1.1701 1.1970 1.1970 5.00 1.1746 1.2025 1.2025 5.20 1.1777 1.2065 1.2065 5AO 1.1799 1.2090 1.2090 5.60 1.1795 1.2085 1.2085 5.80 1.1850 1.2192 1.2192 6.00 1.1969 1.2328 1.2328 6.20 1.2090 1.2445 1.2445 6.40 1.2167 1.2532 1.2532 6.60 1.2252 1.2579 1.2579 6.80 1.2287 1.2608 1.2608 7.00 1.2289 1.2597 1.2597 7.20 1.2261 1.2546 1.2546 7AO 1.2216 1.2486 1.2486 7.60 1.2119 1.2367 1.2387 7.80 1.2026 1.2248 1.2246 8.00 1.1912 1.2109 1.2109 8.20 1.1167 1.1922 1.1922 8.40 1.1635 1.1745 1.1745 8.60 1.1530 1.1578 1.1578 8.80 1.1436 1.1449 1.1449 9.00 1.1392 1.1420 1.1420 9.20 U424 11528 1.1528 9.40 1.1520 1.1920 1.1920 9.60 1.1907 1.2370 1.2310 9.80 1.2284 1.2150 1.2750 10.00 1.2614 1.3090 1.3090 10.20 1.2952 1.3400 1.3400 1OAO 1.3221 1.3684 1.3684 10.60 1.3504 1.3981 1.3981 10.80 1.3675 1.4189 1A189 11.00 1.3765 1A327 lA327 11.20 1.3498 1.4097 1.4097 11AO 1.3487 1.4056 1.4056 11.60 1.3296 1.3896 1.3896 11.80 1.3191 1.3605 1.3805 12.00 (core top) 1.3108 1.3773 1.3773 Note: W(Z} values at 20000 !\IIVVUfllll ru may be applied to cycle burnups greater than

COLR BRAIDWOOD 1 Revision! I Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCo(z) 0 1.0200 150 1.0200 600 1.0567 854 1.0638 1030 1.0668 1270 1.0615 1558 1.0500 2086 1.0300 2300 1.0240 2614 1.0200 3142 1.0200 3560 1.0225 4050 1.0200 17395 1.0200 18050 1.0256 18627 1.0290 19000 1.0293 19500 1.0279 20563 1.0200 25486 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burn ups.

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 I Revision 11 Page 10 oftS CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE t 8 N

2.7 Nuclear Enthalpy Rise Hot Channel Factor (F 6tll (LCO 3.2.2) 2.7.1 FN AH :s; 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:

UPilHm  :::: Base FN AH measurement uncertainty:::: 1.04 when PDMS is inoperable (U FAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN AH Warning Setpoint :::: 2% FN AH Margin FNAH 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 full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.8.

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 lDNBR) 2.9.1  :?: 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 I Revision II Page II of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 Figure 2.8.1.a:

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

Axial Flux Difference Limits with PDMS Inoperable 120

(-15 100) (+10, 00) 100 Unacc ~ptabh Ope ation I V \ Una ccepta pie O. )eratio ~

80

..J

E a:::

w 60

,V A ~cepta lie C perati( n I \ ~

l:

l-e I

/ \

w I-

<< (-3 P, 50' I I (+ 25,5( 1)

-a:::

0~

0 40 I

I I I

20 I

I o i

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

COLR BRAIDWOOD I Revision I J Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 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 120 I II

(-10,1 100 )

100 --~:-

a:; I i

unaceePtabl~

I w

0 una9cep~abl~

a.. 80 Op~ratlon j OPI ration i

..J  !

<< I

i!!l I I

a:: I w 60 L I

l: I l-e w

I- (-20,

....~0 40

~

C) 20 o

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

.--~~-- - .. -~--~-~-.~~~~.-~~-- -~ .- ~--. ~~-~ ~ ..

COLR BRAIDWOOD 1 Revision 11 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 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 Kl shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint T avg coefficient K2 shall be equal to 0.0297/ of.

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

2.10.4 The nominal Tavg 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 AT lead/lag time constant 1:1 shall be equal to 8 sec.

2.10.7 The measured reactor vessel AT lead/lag time constant 1:2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel AT lag time constant 1:3 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant 1:4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature leadllag time constant 1:sshall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 1:6 shall be less than or equal to 2 sec.

2.10.12 The f1 (AI) "positive" breakpoint shall be +10% AI.

2.10.13 The f1 (AI) "negative" breakpoint shall be -18% AI.

2.10.14 The f1 (AI) "positive" slope shall be +3.47% I  % AI.

2.10.15 The fl "negative" slope shall be -2.61 % I AI.

COLR BRAIDWOOD I Revision 11 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 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 ~ shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg ratellag coefficient Ks shall be equal to 0.021 of for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to o1 of for decreasing Tavg.

2.11.4 The Overpower AT reactor trip setpoint T avg heatup coefficient Ks shall be equal to 0.002451 of when T > T".

2.11.5 The Overpower AT reactor trip setpoint T avg heatup coefficient Ks shall be equal to 0 1°F when T:s;T".

2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 of.

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 leadllag time constant '2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel AT lag time constanh 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 '1:1 shall be equal to 10 sec.

2.11.12 The f2 (AI) "positive" breakpoint shall be 0 for all AI.

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

2.11.14 The f2 (AI) "positive" slope shall be 0 for all AI.

2.11 15 The f2 "negative" slope shall be 0 for all AI.

COLR BRAIDWOOD 1 Revision II Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 18 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling {ON B) 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:s; 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action 8.2 and TRM TLCO 3.1. k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the applicable value given in the Table below.

COLR Conditions Boron Concentration Section (ppm) 2.13.1 a) prior to initial criticality 1715 b) for cycle burnups:?: 0 MWD/MTU 1839 and < 16000 MWD/MTU c) for cycle burnups:?: 16000 1520 MWD/MTU 2.13.2 a) prior to initial criticality 1772 b) all other times in life 2028

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 17 EXELON TRACKING 10:

COLR BRAIDWOOD 2 REVISION 7

COLR BRAIDWOOD 2 Revision 7 Page I of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 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))

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

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 (BOPS)

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (ON B) 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 3.1.1 Borated Water Sources - Operating TRM TLCO 3.1.g Position Indication ",\I"r.::".,... - 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 Indication :-"I<<TI Shutdown ::;OE!Clal Test I-Y("",nt,I"I

COLR BRAIDWOOD 2 Revision 7 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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.

2471 psia 2250 psia 0')

Figure 2.1.1: Reactor Core limits

COLR BRAIDWOOD 2 Revision 7 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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'lklk (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'lklk (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/HlP-MTC upper limit shall be +1.799 x 10-5 L'lklkl°F.

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

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

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

where: BOl stands for Beginning of Cycle Life ARO stands for All Rods Out HlP stands for Hot lero 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 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 n\f<~n"'n 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 7 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Figure 2.5.1 :

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%,224) (77%,224)

L L 220 .

/

V /

/

200

,I

~ANKB I ,I V

180 C

~

... 160 V V (100%, 161)

IL IU

'0 J:

~ 140

!/(0%,162)

/

IBANK C I

/

/ /

f/)

Q.

(I)

~ 120 s:: t'

I 0

"iii 0 100

/' /

~

Q.

I s::

IU IXl 80 / 1/ / IBANKD "C

0 a:: V I V 60 / L 40

/

'1(0%,47) I

./

V 20 I

I V I I

1(30%,0)V, I 0 I o 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

COLR BRAIDWOOD 2 Revision 7 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 2.6 Heat Flux Hot Channel Factor (FQ@(LCO 3.2.1) 2.6.1 Total Peaking Factor:

F RTP FQ(Z) s -Q-xK(Z) for P sO.S O.S F RTP FQ(Z) s -(-~-xK(Z) for P > O.S 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 1.1 1(0.0, 1.0) .1 (6.0, 1.0) I 1

1(12.0,0.924)1 0.9 0.8 NO.7 a

I.L "0

.~ 0.6

'is E

o 0.5 z

I r-I N ....... LOCA Limiting Sl OA ,

Envelope 0.3 0.2 0.1

--l.--

BOTTOM Core TOP

COLR BRAIDWOOD 2 Revision 7 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 burnups 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 z 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 Full Power Days (EFPD). These values shall be used to increase the FWo(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 Fa 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:

COLR BRAIDWOOD 2 Revision 7 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.S.l.a (Top and Bottom 8% Excluded per WCAP-10216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 000 (core bottom) 12875 1.4463 IA340 14172 0.20 1.2772 IA 175 1.4200 1.3924 0.40 1.2740 1.4005 1.4030 1.3792 0.60 1.2698 1.3866 1.3870 1.3687 0.80 1.2558 1.3654 1.3530 1.3432 1.00 1.2465 1.3486 1.3410 1.3247 1.20 1.2488 1.3320 1.3250 1.3153 1.10 1.2598 1.3231 1.3130 12995 160 1.2461 1.3017 12970 1.2786 1.80 1.2337 12821 1.2830 1.2604 2.00 1.2207 1.2615 1.2680 1.2401 2.20 1.2059 1.2383 1.2490 L2177 2.40 1.1926 1.2175 1.2389 1.1982 2.60 1.1768 1.1958 1.2262 Ll820 2.80 1.1694 1.1796 12142 Ll720 3.00 Lt618 1.1758 1.2020 1.1660 3.20 Ll531 1.1719 Ll871 1.1625 3.40 Ll475 U675 1.1736 Ll600 3.60 Ll426 1.1616 1.l616 1.1625 3.80 11375 1.1557 I 1.1594 Ll647 4.00 1.1332 1.1493 1.1563 1.1652 4.20 Ll339 Ll409 L1517 Ll668 4.40 1.1345 1.1325 1.1471 1.1714 4.60 Ll341 L1231 1.1410 Ll820 4.80 1.1328 Ll137 1.1338 1.1905 5.00 1.1304 Ll037 1.1257 1.1969 5.20 1.1270 1.0962 11280 1.2026 5.40 Ll227 1.0913 1.1314 1.2059 5.60 LI231 I 1.0876 1.1327 1.2063 5.80 U300 Ul917 11322 1.2109 6.00 1.1366 10972 U432 1.2268 6.20 Ll414 1.1043 1.1574 l.2397 6.10 11451 UIlO 1.1694 1.2505 6.60 Ll479 LlI77 L1784 12561 6.80 1.1487 L1234 Ll855 12599 7.00 U495 lJ282 Ll906 1.2607 720 U474 U345 U918 1.2565 7AO US6S 11449 Ll920 1.2505 7.60 1.1655 1.1536 US82 12404 7.80 1.1738 Ll617 L1836 1.2286 8.00 1.1812 1.1694  !.l76l 1.215]

8.20 1.1870 1.1748 1.1655 1.1977 8.40 L1924 Ll869 U543 1.1793 8.60 U957 1.2003 L1391 Ll579 8.80 U995 Un3 U345 1.1366

'HIO 12019 12247 l.I392 U260 9.20 UllO 12354 lI443 L1430 3

9.40 12222 l.2522 U532 1.1762 9.60 1.2315 12674 U600 12203 9.80 L2477 12811! 1.2584 lOOO 12523 12955 12068 L2924 HUO L2597 13075 1.2398 13215 10.40 1.2577  !.3 1O0 l.2631 1.3444 10.60 1.2327 13055 L2845 1.3620 10.80 1.2356 13037 1.2958 1.3815 11.00 1.2318 13136 12937 1.3985 11.20 1.2407 1.3177 1.2817 1.3986 IIAO 12411 1.3300 1.2884 13930 11.60 1.2445 L3359 1.2720 1.3875 11.80 1.2498 1.3426 12651 1.3787 12.00 (core tovl 1.2574 l.3584 12594 1.3764 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than

COLR BRAIDWOOD 2 Revision 7 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Table 2.6.2.b EOL-only W(Z) versus Core Height for AFO Acceptable Operation Limits in Itigure 2.8.l.b (Top and Bottom 8% Excluded per WCAP-!0216 Height 18000 20000 25330 (feet) MWO/MTlJ MWOfMTlJ MWO/MTlJ 0.00 (core bottom) 1.2765 L2566 1.2566 0.20 1.2625 1.2370 1.2370 OAO 12501 1.2263 1.2263 0.60 1.2395 L2180 1.2180 0.80 1.2092 1.1977 1.1977 1.00 I.! 941 1.1829 1.1829 1.20 !l855 1.1770 11770 lAO I.! 761 I.! 646 1.1646 1.60 Ll650 Ll480 Ll480 1.80 Ll591 1.1400 1.1400 2.00 1.1526 1.1328 1.1328 2.20 1.1456 1.1251 1.1251 2.40 1.1394 1.1193 1.1193 2.60 I.! 349 Ll180  !.lISO 2.80 Ll311 LlI87 L1187 3.00 Ll287 LlI84 Lll84 3.20 L!260 1.1182 I LlI82 3.40 U273 1.1230 Ll230 3.60 1.1277 1.1268 1.1268 3.80 Ll278 L!296 Ll296 4.00 Ll342 1.1445 1.1445 4.20 Ll400 L 1586 Ll586 4.40 Ll463 U714 LI714 4.60 Ll559 1.1820 LI820 4.80 1.1631 Ll905 Ll905 5.00 1.1687 l.l969 1.1969 5.20 11733 1.2026 1.2026 SAO 1.1771 1.2059 1.2059 5.60 Lt783 1.2063 12063 5.80 1.1803 L2!09 L2109 6.00 Ll943 1.2268 L2268 6.20 L2081 1.2397 1.2397 6.40 1.2197 L2505 L2505 6.60 L2267 L2561 L2561 0080 12319 L2599 1.2599 7.00 L2344 1.2607 12607 720 L2320 L2565 1.2565 7.40 l.2281 12505 1.2505 7.60 l.2200 ].2404 L2404 7.80 UI03 1.2286 1.2286 8000 1.1983 L2151 1.2151 8.20 1.1823 11977 Ll977 8.40 L1646 Ll793 L1793 8.60 Ll431 Ll579 1.1579 UO 1.1273 1.1366 1.1366 9000 11230 1J260 U260 920 Ll347 Ll430 1.l430 9.40 LlS66 1.1762 U762 9.60 U834 L2203 12203 980 12138 12584 12584 10.00 1.2463 1.2924 1.2924 10.20 1.2792 1.3215 I 13215 10040 1.3042 13444 1.3444 10.60 13256 1.3620 1.3620 10080 1.3425 1.3815 103815 11000 1.3499 13985 1.3985 11.20 1.3429 1.3986 L3986 11 AD 1.3414 1.3930 1.3930 11.60 1.3295 1.3875 L3875 11.80 1.3204 1.3787 1.3787 12.00 (core top) 1.3151 1.3764 L3764 20000

COLR BRAIDWOOD 2 Revision 7 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Table 2.6.2.c Penaltv Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) Feo(z) 0 1.0200 501 1.0200 677 1.0268 853 1.0350 1029 1.0410 1204 1.0460 1380 1.0490 1556 1.0470 2786 1.0200 11925 1.0200 12101 1.0211 12452 1.0222 12628 1.0224 13155 1.0211 13331 1.0200 17901 1.0200 18076 1.0225 18779 1.0223 18955 1.0210 19131 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All outside the range of the table shall use a 2% ~~~,~If" factor for with the 3.2.1.2 Surveillance Requirements.

COLR BRAIDWOOD 2 Revision 7 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 N

2.7 Nuclear Enthalpy Rise Hot Channel Factor (F M:Jl (LCO 3.2.2)

N 2.7.1 F hH ::; F~~P[1.0 + PFhH(1.0- P)]

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

2.7.2 Uncertainty

The uncertainty, UFhH , to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNL\H shall be calculated by the following formula:

where:

UFLlHm = Base FNL\H measurement uncertainty = 1.04 when PDMS is inoperable (U FhHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FNL;H Warning Setpoint = 2% FNhH Margin

=

FNhH Alarm Setpoint 0% FNL;H 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 2.9.  ?:': 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsL ) is applicable with THERMAL POWER

?:': 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

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

COLR BRAIDWOOD 2 Revision 7 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Figure 2.8.1.a:

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

Axial Flux Difference Limits with PDMS Inoperable 120

(-15 100) (+10, ~OO) 100 0::

W 3:

Unacc eptabl~

Ope ation J I \ Una ccepta lie 0 eratio 1 80 1/

0 D..

..J

~

!E 0::

~cepta ~Ie I

peratic n \\

W 60 J:

l-e w

/  !

\

I-(+ 25,5( J)

-~

0~

0 40

(-3 5.50' I

I 20 I I I I I

I

)

o

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

COLR BRAIDWOOD 2 Revision 7 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 I I I ~ I (-1 0, 100)

~ 100 unaLptablj -~;-~-

~ 80 --- 0~ion I-----*~*-~I--+-- +~

~ !i I AccJptable 0::: Opdration

~ 60 I

~

i i

l - - -.......-..,.I....(-_2--f,j50) I --:-

0 1+25, 5P) _

~

o

'i:f!.

~ 1! ~. I I I 20 I

I I

o

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

COLR BRAIDWOOD 2 Revision 7 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 2.10 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overtemperature ~T Setpoint Parameter Values 2.10.1 The Overtemperature ~T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature ~T reactor trip setpoint Tav9 coefficient K2 shall be equal to 0.0297/ of.

2.10.3 The Overtemperature ~T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135/ psi.

2.10.4 The nominal Tav9 at RTP (indicated) T' shall be less than or equal to 588.0 of.

2.10.5 The nominal ReS operating pressure (indicated) pr shall be equal to 2235 psig.

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

2.10.7 The measured reactor vessel ~ T lead/lag time constant 1:2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel ~ T lag time constant 1:3 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant 1:4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant 1:5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 1:s shall be less than or equal to 2 sec.

2.10.12 The f1 (~I) "positive" breakpoint shall be +10% ~I.

2.10.13 The f1 (~I) "negative" breakpoint shall be -18% ~I.

2.10.14 The f1 (~I) "positive" slope shall be +3.47% I % ~1.

2.10.15 The f1 (~I) "negative" slope shall be -2.61 % I % ~l.

COLR BRAIDWOOD 2 Revision 7 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 2.11 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overpower £1T Setpoint Parameter Values 2.11.1 The Overpower £1T reactor trip setpoint ~ shall be equal to 1.072.

2.11.2 The Overpower £1 T reactor trip setpoint Tav9 rate/lag coefficient K5 shall be equal to 0.021 of for increasing Tavg 2.11.3 The Overpower £1 T reactor trip setpoint Tav9 ratellag coefficient Ks shall be equal to o / OF for decreasing T avg 2.11.4 The Overpower £1 T reactor trip setpoint Tavg heatup coefficient Kt, shall be equal to 0.002451 OF when T> Til.

2.11.5 The Overpower £1T reactor trip setpoint T avg heatup coefficient Kt, shall be equal to 0 I OF when T ::;;T".

2.11.6 The nominal Tavg at RTP (indicated) Til shall be less than or equal to 588.0 OF 2.11.7 The measured reactor vessel £1T leadllag time constant 1:1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel £1 T leadllag time constant 1:2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel £1 T lag time constant 1:3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant 1:6 shall be less than or equal to 2 sec.

2.11 11 The measured reactor vessel average temperature rate/lag time constant 1:7 shall be equal to 10 sec.

2.11.12 The f2 (£11) "positive" breakpoint shall be 0 for all £11.

2.11.13 The f2 (£11) "negative" breakpoint shall be 0 for all £11.

2.11.14 The f2 (£11) "positive" slope shall be 0 for all £11.

2.11.15 The f2 (£1l) "negative" slope shall be 0 for all £11.

COLR BRAIDWOOD 2 Revision 7 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 (Tavg) 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 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 s 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 Conditions Section (ppm) 2.13.1 a) prior to initial criticality 1678 b) for cycle burnups ;::: 0 MWD/MTU 1796 and < 16000 MWD/MTU 1506 c) for Cycle Burnup;:: 16,000 MWD/MTU 2.13.2 a) prior to initial criticality 1747 all other times in life 1992

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