BYRON 2002-0100, Cycle 11 Core Operating Limits Report

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Cycle 11 Core Operating Limits Report
ML022800028
Person / Time
Site: Byron Constellation icon.png
Issue date: 09/27/2002
From: Lopriore R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.01.0700, BYRON 2002-0100
Download: ML022800028 (18)
v • d • e


Text

Exelon Generation Company, LLC wwwexeloncorpcom Exelknm.

Nuclear Byron Station 4450 North German Church Road Byron, IL61010-9794 September 27, 2002 LTR: BYRON 2002-0100 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455

Subject:

Byron Station Unit 2 Cycle 11 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

we are submitting the Unit 2 Cycle 11 COLR.

Should you have any questions concerning these reports, please contact William Grundmann, Regulatory Assurance Manager, at (815) 234-5441, extension 2800.

ctfully, d Loprior Site Vice President Byron Nuclear Generating Station

Attachment:

1) Byron Station Unit 2 Cycle 11 COLR RPUJL/rah cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector- Byron Station NRC Project Manager- NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

ATTACHMENT Byron Station Unit 2 Cycle 11 Core Operating Limits Report

- % _J_

"BY2CIICOLR, Rev. 0 Page 1 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1 1.0 CORE OPERATING LIMITS REPORT prepared in This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 11 has been 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 3.1.61 Control Bank Insertion Limits LCO 3.1.8 Physics Tests Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN6H)

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) from LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration this report are listed below:

The portions of the Technical Requirements Manual affected by 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)

- I d, "BY2C]I COLR, Rev. 0 Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 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 Safeiy Limits (SLs) (SL 2.1.1) 2.1.1 In Modes 1 and 2, the combination of Thermal Power, Reactor Coolant Systerp (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.11.

680 2471 psia 660 "640 E= ______

' 20

. 1.

0,*A Fraction of Nominol Power Figure 2.1.1: Reactor Core Limits

"BY2CII COLR, Rev. 0 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 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% 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 SDM limit for MODE 5 is:

2.2.2 SbM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM I 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 +2.72 x 10.5 Ak/k/°F.

2.3.2 The EOL/AROIHFP-MTC lower limit shall be -4.6 x 10-4 Ak/k/°F.

2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be

-3.7 x 10.4 Ak/k/°F.

0 2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 Ak/k/ F.'

where: BOL stands for Beginning of Cycle Life of 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 Shutdovwn 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 the 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 a 113 Step overlap limit.

BY2C] I COLR, Rev. 0 Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1I Figure 25.1 Control Bank Insertion Units Versus Percent Rated Therrrd Power (27D/,; 224) (77r/ 224) 224 220 200 180 S160 (100%P/q 161)

~140 CLS120 0

0.

,C 80

  • 60 40 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Relative PIw (Percent)

BY2C II COLR, Rev. 0 Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 2.6 Heat Flux Hot Channel Factor (FfZ)} (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FQ(Z) *- .5xK(Z) forP_50.5 0.5 1 FP where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F RTP= 2.60 KjZ) is provided in Figure 2.6.1.

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 in Figures 2.6.2.a through 2.6.2.d.

The norrhal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.

Table 2.6.2 shows the FCo(z) penalty factors that are greater than 2%,per 31 Effective Full Power Days. 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 "cycleburnups that are outside the range of Table 2.6.2.

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:

UFQ = Uq,,

  • U, where:
  • Uqu = Base FQ 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:

FQ(Z) Warning Setpoint 2 2% of Fo(Z) Margin FQ(Z) Alarm Setpoint > 0% of Fo(Z) Margin

BY2CI I COLR, Rev. 0 Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1I Figure 2.6.1 K(Z) - Normalized Fo(Z) as a Function of Core Height 1.1 (0.0 1.0))

,0.924) 0.9 0.8 N 0.7 a

U

' 0.6 E

o 0.5 Z

N LOCA Limiting!

S0.4 -L_ Envelope I 0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 10 11 12 BOTT'OM Core Height (ft) TOP

BY2CI I COLR, Rev. 0 Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II Height KAW W(z)

F eet Byrn WUit 2 Cyde 11 000 10000 020 10000 Flgure2 62 o 040 10000 060 1 0000 d y W(Z) F urncbn d 150 MVVDmI"U S rncri 0 80 1 0000 (UcpcndI8cBia. 15% ExducLbdper WCAP-10216) 100 1.0000 1.20 10000 140 , 10¢000 1.0000 16o 1.35 180 1.2123 200 '1 1939 2.20 1.1773 2A0 11617 260 1.1456 280 1.1389 3aol 1.1378 320 1.1357 1.30 340 1.1328 360 1.1296 380 1 1322 400 1.1337 420 1.1362 440 1.1366 460 11371 4 80 1.1357 1.25 500 1.1344 520 1.1310 540 1.1266 5.60 1.1305 z

580 1.1361 600 1.1417 C,.)

620 1.1521 1.1619 n 1.20 640 L .

660 1.1707 680 1.1785 7.00 1 1846 7.20 1.1896 7.40 1.1942 7.60 1.1987 7.80 1.2070 1.15 8W0 1.2137 820 1.2174 840 1.2221 860 1.2273 880 1.2353 9W0 1.2455 9.20 12564 940 12677 1.10 960 1.2783 980 1.2816 lOW0 1.2777 1020 1.2736 1040 10000 1060 1 0000 1080 1 0000 1100 1 0000 1.05 1120 1.0000 000 2.00 4 00 6 00 8.00 1000 12.00 11.40 1.0000 11.60 10000 CORE HEIGHT (FEET) 11 80 1OO0 1200 10000

BY2CI I COLR, Rev. 0 Page 8 of 16 I

CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I I Hegt Ax W(Z)

Feel Byrcn Ur-t2 Cyde 11 000 1 0000 020 10000 Figure262 b 040 1 0000 060 1 0000 S uTrray of W(Z) F utrdn cl 6000 MWDVMv'U 080 1 0000 (FcpcndBcttln 15% Excudedupc WCAP-10216) 100 1 0000 120 1 0000 140 10000 1 0000 1.35

_L~ flii 1.60 180 200 220 240 1.1998 1.1853 1.1698 1.1552 I :L12 2.60 1.1400 280 1.1303 300 1.1267 3.20 3 40 1.1214 1.1161 1.30 TIL1Th"IT T IL 360 1.1089

_7 iii 380 1.1069 400 1.1065 I" 420 1.1041 440 460 1.1026 1.1018 1 1 'I I LI ,+/-o--*

1.0993 1.25 480 500 1.0965 IV7I I .ji !i ,+~L i

5.20 540 1.0916 1 0870 JL!- 'I 4, 4~ - - +/-

560 1.0818 z t -t

,f --

580 600 620 1 0855 1 0984 1.1181 0

z* 1.20 * '-Z

. .I-.i I- i

,,iL,-' ..- *-L, i° li'i 640 1.1357 660 1.1516 680 2.1664 7.00 1.1802 7.20 1.1928 7.40 1.2058 7.60 1.2158 7.80 1.2258 1.15 800 820 840 1.2339 1 2409 1.2479

-LC*. ... D02 L4-.. 4.1..

0-

.... 4 444.-T 860 1 2509 I~iiI-**

'I i-i

.... .-i-- ,.4-4-4 880 900 1 2593 1.2676 -- !-1 i-v, IG i

920 11751 C(E 940 1.2833 1.10 12937 20 00 400 60 800 - 100 120 960 9.80 1000 1.3056 1.3173 AACORE* HEIGHT (FET 1020 1.3267 1040 1 0000 1060 1.0000 1080 1.0000 1 0000 1.05 1100 11.20 1 0000 11.40 1 0000 1160 1 0000 1180 I 0000 1200 I 0000

BY2CI I COLR, Rev. 0 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1I Heght MAX W(7)

Feet Byrcn Unit 2 Cyde 11 000 1 0000 Figre262 c 020 1.0000 040 1.0000 0160 1 0000 S wurnmyc W(Z) Functon ti14000 MDMT U 080 10000 (rcpcndBcftrT 15% ExducldP WCAP-10210) 100 10000 1.20 10000 1An 1.9000 1 60000 1.35 1.80 1.2610 2W0 1.2520 2.20 1.2400 240 1.2298 260 12204 280 1.2133 300

..2-il ,-H-4 1.2047 1.30 320 340 1.1943 1 1845 I..

1j l L d 360 1.1722 380 400 420 11668 1 1639 1 1583 4 --. fIL1i 1144---

440 1.1534 I .

460 1.1470 1.1396 1.25 480 i ______!

5W0 1.1319 520 540 560 580 1.1225 1.1248 1.1274 1.1290 0 111 l~wA"~i

-4...-,- .... 4 , 4 Q-I'I

.r

-i

"-"-4 I-600 1.1296 C.)

6.20 1.1272 z: 1.20 6.4O 6.60 1.1248 1.1197 LL IL j  !LL I '1II 680 1.1145 7.00 1.1176

" . ' I . 1~i j . . . ..L4~i~ -i i!... rK L.

7.20 1 1236 7AO 1 1305 760 1 1346 780 11386 1.15 800 1.1417 820 1.1429 840 .1.1430 860 1.1443 8 80 1.1464 900 1.1475 920 1.1515 11566 1.10 940 S

  • I 960 1.1643 9.80 1.1700 1000 1.1755 1020 12002 1040 10000 1060 1.0000 1080 10000 1100 I.OO0 1.05 11.20 1.0000 0.00 2.00 4.00 600 800 10.00 12.00 1140 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 1.0000 1200 1.0000

Page 10 of 16 "BY2CII COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 He~gN MAX WZ)

Feet ByrcnUnt2 Cyde 11 10000 000 Fig.ie 2 6 2.d 0 20 1.0000

",040 10000 10000 Surrnay c W(Z) Funrti ct 20000 MWDiMI" U 060 080 10000 (I cp*-)dBcttcm 15% Exducbdper WCAP-10216) 100 10000 120 1.0000 1.40 10000 160 1.0000 1.35 180 1.*735 200 12630 1*487 2.20 1.23352 2.40 2.60 1.2171 i."--" . ...- ..

280 1.2027 ... .II . . .. 1 300 11874 1.1715 1.30 320

'340 1.1703 m i I 360 1.1686

!* !* * .- ---i-.. . ..

380 400 1.1669 1.1637 'i*t . . . ,I 420 1.1611 440 1.1651 460 1.1742 1.18 14 1.25 480 500 520 1.1857 1.1898

--I t f _ __

I i

r

.2 540 1 1933 560 1.1939 580 1.1925 1 1890

+_--1--4 1._.... L---:- j.... *1 600 C,.)

620 1 1826

  • 1.20 6.40 1.1787 660 1 1875 1.1938

, , II i S I I 680 7.00 1.1991 720 11019 7.40 1.2027 760 1.2007 7.80 1.1981 1.15 800 1 1936 .L' 1 i ii 820 1.1848 II II  ! ~ ,____ _____

840 1.1 777 860 1.1674 880 1.1570 9.00 1.1494 9.20 1.1467 9.40 1.1478 1.10 960 1.1690 9.80 1.2070 1000 1.2410 II 1020 1040 1.2710 10000 i 1060 1.0000 1080 10000 1100 1.0000 1.05 11 20 1 0000 0.00 2.00 4 00 6.00 8.00 1000 12.00 1140 1 0000 CORE HEIGHT (FEET) 11.60 10000 1180 10000 1200 1 0000

Page 11 of16 BY2CI I COLR, Rev. 0 1

CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor -F e(z)

(MWDIMTU) (%)

322 2.00 493 2.55 665 2.74 837 2.76 1008 2.74 1866 2.58 2210 2.58 2896 2.74 3068 2.75 3239 2.72 3411 2.65 3754 2.30 4097 2.00 11821 2.00 11992 2.11 12335 2.84 12507 2.89 12679 2.87 2.71 12850 13537 2.00 Notes:

cycle burnups.

Linear interpolation is adequate for intermediate shall use a 2% penalty factor for compliance with All cycle burnups outside the range of the table the 3.2.1.2 Surveillinice Requirements.

Page 12 of 16 BY2CI I COLR, Rev. 0 CYCLE II CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 3.2.2) 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNA* (LCO 2.7.1 FNMH < FRTP H [1.0 + PFH(t .0 - P)]

POWER where: P = the ratio of THERMAL POWER to RATED THERMAL FRTPAH = 1.70 PFNH = 0.3 2.7.2 Uncertainty when PDMS is inoperable Rise Hot Channel The uncertainty, UFaH, to be applied to the Nuclear Enthalpy Factor FNH shall be calculated by the following formula:

UFH -- UFAHm where:

UF,,Hm = Base FNH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNAH Warning Setpoint Ž_2% of FNmH Margin FNH Alarm Setpoint 2 0% of FN,,H Margin 2.8

.3 Axial Flux Difference (AFD) (LCO 3.2.3)

(AFD) Acceptable 2.8.1 When PDMS is Inoperable, the AXIAL FLUX DIFFERENCE valid PDMS or the latest Operation Limits are provided in Figure 2.8.1 Surveillance Report, whichever is more conservative.

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

2.9 Departure from Nucleate Boiin i Ratio(DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL -I 1.536 is applicable with THERMAL POWER The Axial Power Shape Limiting DNBR (DNBRAPsL)

> 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

DNBR Warning Setpoint >_2% of DNBR Margin DNBR Alarm Setpoint Ž-0% of DNBR Margin

BY2CI I COLR, Rev. 0 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II Figure 2.8.! Axial Flux Difference Limits as a Function of Rated Thermal Power Axal Fux Difference Units with PI',S Inoperable 120.

0 6 ,

V40 "020 40 20 -10 0 10 20 30 40 50 AIIAL MM .(UX OFFJ E (0/4

BY2CI 1 COLR, Rev. 0 Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 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 Ta,,g 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 0.00181 / 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 "c 1 shall be equal to 8 sec.

2.10.7 The measured reactor vessel AT lead/lag lime constant'"2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel AT lag time constant 13 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant "r4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant 'r 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 f1 (Al) "positive" breakpoint shall be +10% Al.

2.10.13 The f, (Al) "negative" breakpoint shall be -18% Al.

2.10.14 The fI (Al) "positive" slope shall be +3.47% /% Al.

2.10.15 The f, (Al) "negative" slope shall be -2.61% 1% Al.

"BY2CII COLR, Rev. 0 .Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoirt Paramejer. Values 2.11.1 The Overpower AT reactor trip selpoint K, shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Ta.g rate/lag coefficient K5 shall be equal to 0.02 / OF for increasing T.v,.

2.11.3 The Overpower AT reactor trip setpoint Taro rate/lag coefficient K5 shall be equal

,g.

0 /P.Ffor decreasing Ta 2.11.4 Tile' Overpower AT reactor trip setpoint T.,, heatup coefficient K6 shall be equal

.to 0.00245 1 "F when T > T1".

2.11.5 The Overpower AT reactor trip setpoint Ta,, heatup coefficient K6 shall be equal to.0 / OF when T <TP".

2.11.6 The nominal Ta,, at RTP (indicated) To shall be less than or equal to 588.0 OF.

2.11.7 The measured reactor vessel AT lead/lag time constant -E,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 ' 3 shall be less than or equal S3to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant -16 shall be less than or equal to 2 sec.

The measured reactor vessel average temperature rate/lag time constant t7 2.11.11 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.

.; . . in "BY2CI I COLR, Rev. 0 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boilinq (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 2,) 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 380,900 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1753 ppm (LCO 3.9.1).

and control 2.13.2 The Reactor Coolant System boron concentration, with all shutdown rods fully withdrawn, shall be greater than or equal to 1803 ppm prior to initial criticality of Cycle 11, or greater than or equal to 2048 ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during of rod drop time measurements and during the surveillance of performance Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3.1.g and 3.1 .k).

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