ML021230336

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Core Operating Limits Report Cycle 10 Sequence Number 4
ML021230336
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 04/18/2002
From: Vonsuskil J
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW020028
Download: ML021230336 (19)
v • d • e


Text

Exelonm.

Exelon Generation Company, LLC www exeloucorp-corn N uclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-458-2801 April 18, 2002 BW020028 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 1 Cycle 10 Sequence

Subject:

Core Operating Limits Report, Braidwood Unit Number 4 Core Operating Limits Report (COLR) for Braidwood The purpose of this letter is to transmit the with Technical Specification 5.6.5, "Core Unit 1 Cycle 10 Sequence Number 4, in accordance COLR was recently implemented and of the Operating Limits Report (COLR)." This revision provides additional information and clarification.

please contact Ms. A. Ferko, Regulatory If you have any questions regarding this matter, Assurance Manager at (815) 417-2699.

Respectfully, Jýs D. onSuskil Site Vice President Braidwood Station 1 Cycle 10 Sequence

Attachment:

Core Operating Limits Report, Braidwood Unit Number 4 cc: Regional Administrator - NRC Region III Station NRC Senior Resident Inspector - Braidwood

ATTACHMENT I Core Operating Limits Report Braidwood Unit 1, Cycle 10, Sequence Number 4

NUCLEAR FUEL MANAGEMENT DEPARTMENT TRANSM17ITAL OF DESIGN INFORMATION

[ SAFETY RELATED Originating Organization TODI No NFMO100083 o NON-SAFETY RELATED 0 Nuclear Fuel Management Seq No 4 O' REGULATORY RELATED C Other (specify) Page 1 of 17 Station Braidwood Unit I Cycle 10 Generic To: Lonnie K. Kepley - Braidwood Subject Braidwood Unit I Cycle 10 Core o~tin[ Limits Report in ITS Format and W(z) Function Tyrone Stevens Preparer Prepa's Signature DA Peter Moravek kP Reviewer leev*iewr's Signature .. .

Bob Tsai NFM Supervisor A-t 1-Supervisor's Signature Date Status of Information: 0 Verified Ol Unverified o Engineering Judgement Method and Schedule of Verification for Unverified TODIs:

Description of Information:

Attached is the Braidwood Unit I Cycle 10 Core Operating Limits Report (COLR) in the ITS format and W(z) function Sequence 4 of this TODI supersedes Sequence 3 Purpose of Information:

The attached Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 10 has been prepared in accordance with the requirements of Technical Specification 5 6 5 (ITS) In this sequence, the following COLR Sections were revised:

- Section 2 5 1, the control bank insertion limits, applicable for LCO 3 1 6

- Section 2 5 4, the control bank overlap limits, applicable for LCO 3 1 6

- Section 2 13 2, the Rector Coolant System boron concentration, applicable to TLCO 3 1 k 2 Braidwood Station is requested to perform a plant review of this document Upon completion of the plant review, Braidwood Station is to transmit the COLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 5 6 5 Please provide NFM (Tyrone L Stevens) with a copy of Braidwood Station's completed plant review and COLR submittal to the NRC Source of Information:

1 Westinghouse Letter 01-CB-G-151, "Braidwood Unit I Cycle 10 COLR Data", dated August 28, 2001 2 Westinghouse Letter 01-CB-G-153, "Braidwood Unit I Cycle 10 COLR Revision 1", dated August 31, 2001 3 TODI NFMO100062, Revision 1, "BR1C1O Reload Design Initiation", dated June 12, 2001 4 NFS Calcnote PNDCN:00-003, Rev 0, "Evaluation of SPIL Using 224 Steps Rod Withdrawn as Definition of ARO";

dated May 11, 2000 5 Westinghouse Letter 01-CB-G-132, "Braidwood I Cycle 10 BEACON DMM Model Delivery", dated July 27 2001 6 Westinghouse Letter 0 I-CB-G-155, "Braidwood Unit 1 Cycle 10 Boron Concentration for Startup Physics Testing", dated September 7, 2001

(

Supplemental Distribution: A Ferko / L S Dworakowski (BR)

TODI NFMO100083 Seq 4 Page 2 of 17 CORE OPERATING LIMITS REPORT (cOLR) for BRAIDWOOD UNIT 1 CYCLE 10 10 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 10 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 11 Reactor Core Safety Limits (SLs)

LCO 311 SHUTDOWN MARGIN (SDM)

LCO 3 13 Moderator Temperature Coefficient (MTC)

LCO 314 Rod Group Alignment Limits LCO 315 Shutdown Bank Insertion Limits LCO 316 Control Bank Insertion Limits LCO 318 PHYSICS TESTS Exceptions - MODE 2 LCO 32 1 Heat Flux Hot Channel Factor (FO(Z))

LCO 3 22 Nuclear Enthalpy Rise Hot Channel Factor (FN A)

LCO 323 AXIAL FLUX DIFFERENCE (AFD)

LCO 325 Departure from Nucleate Boiling Ratio (DNBR)

LCO 33 1 Reactor Trip System (RTS) Instrumentation LCO 339 Boron Dilution Protection System (BDPS)

LCO 34 1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 39 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 Ž 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)

TODI NFMO100083 Seq 4 Page 3 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 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 11 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 2471 psia 660 i, 2250 pei 70)

"1640 620 600 580

.2 Fri of .oilPoe 2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

TODI NFMO100083 Seq 4 Page 4 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 1 CYCLE 10 22 SHUTDOWN MARGIN (SDM)

The SDM limit for MODES 1, 2, 3, and 4 is 22 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 If, 3 1 h, and 3 1 j)

The SDM limit for MODE 5 is 2 22 SDM 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) 23 Moderator Temperature Coefficient (MTC) (LCO 3 1 3)

The Moderator Temperature Coefficient (MTC) limits are 23 1 The BOL/ARO/HZP-MTC upper limit shall be +2 14 x 10" Ak/k/JF 232 The EOLIARO/HFP-MTC lower limit shall be -4 6 x 10e Ak/k/ 0 F 233 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3 7 x 104 Ak/k/OF 234 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 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 24 Shutdown Bank Insertion Limits (LCO 3 1 5) 2 41 All shutdown banks shall be fully withdrawn to at least 224 steps 25 Control Bank Insertion Limits (LCO 3 1 6) 25 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 52 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps 2 53 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 54 Each control bank not fully withdrawn from the core shall be operated with the followinI overlap limits as a function of park position.

Park Position (step) Overlap Limit (step) 225 110 226 111 227 112 228 113 229 114 231 116

TODI NFMO100083 Seq 4 Page 5 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 Figre25A:

Control Bank Insertion Un~its Versus Percent Rated Thermal Pomw 224 (270/ 224) (T7., 224) 22)D:_________ - - - ...

200D_

180 --. 0

, 160' (C**, 16)_ (10006161)

~120 0

.10D 0

~80

~6D 0

0 10 2D 30 40 w 0 :0 w*:

0 ::: *~i mii 0 *;::liw 80 9D01400 1.0:0;i:

TODI NFMO100083 Seq 4 Page 6 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 26 Heat Flux Hot Channel Factor (Fq(Z (LCO 3 2 1) 261 F RTP FQ(Z) FTxK(Z)

-5 forP_<05 05 T

FQR P FQ(Z) : Q xK(Z) forP>05 P

where P = the ratio of THERMAL POWER to RATED THERMAL POWER F'= 260 K(Z) is provided in Figure 2 6 1 262 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 262d The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWDIMTU Table 2 6 2 shows the FC%(z) penalty factors that are greater than 2% per 31 Effective Full Power Days These values shall be used to increase the FWQ(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 Multiplication Factor = 1 02 26 3 Uncertainty The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula UFQ= Uq. oU, where Uqu = Base FQ measurement uncertainty = 1 05 when PDMS is inoperable Ue = Engineering uncertainty factor = 1 03 264 PDMS Alarms FQ(Z) Warning Setpoint _>2% of F0 (Z) Margin FQ(Z) Alarm Setpoint Ž_ 0% of F0 (Z) Margin

TODI NFMO100083 Seq 4 Page 7 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT I CYCLE 10 Figure 2.6.1: K(Z) - Normalized FQ(Z) as a Function of Core Height 11 (00a 1) (61,0))

(12 ( ,0 924) 09 08

-N 07 a

£1.

06 E

z"05

-"--LOCA Limiting

  • 04 Envelope 03 02 01 0

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

TODI NFMO 100083 Seq 4 Page 8 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 1 CYCLE 10 Height MAX W(Z) peet Braidwood Unit I Cycle 10 m.oo 1 0000 0.20 1 0000 Figure 2.S."o 0.40 10000 060 1 0000 Summary of W(Z) Function at 150 MWD/MTU 0.80 I 0000 (Top and Bottom 15% Excluded per WCAP- 10216) 1.00 10000 1.20 10000 1.40 10000 1.60 10000 1 35 1.80 11603 2.00 11464 2.20 11381 2.6O 11345 2.60 11285 2.80 1 1242 3.00 11190 3.20 11155 130 5.40 11179 3.60 1 1206 3.80 11225 4.00 11234 4.20 1 1245 ALSO 11248 4.4O 11227 11214 1 25 --- - --

SA0 11202 5.20 1 1205 5.4O 11270 S.60 11336 S.80 11385 z 6.00 11521 6.30 1 1648 0z12 6.40 1 1765 U.

GAO 6.60 11853 11921 T.O0 I 1982 7.20 12050 7.4O 12093 7.60 12131 7.80 1.2158 115 8.OO 1 2154 8.40 8.60 12198 1 2228 z~zz~zz -4 1 2236 2.20 1 2237 9.00 1 2217 9.60 12210 1 2330 110 9.80 1 2450 3.00 13.40 10.00 1 2520 12580 10.110 12660 30.60 10000 10000 110.80 10.30 10000 11.00 10000 1 05 10.40 1.60 10.So 10000 0 00 200 400 600 800 1000 1200 11.40 10000 11.60 10O CORE HEIGHT (FEET) 11.310 10000 12.00 10000.

TODI NFMO100083 Seq 4 Page 9 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 Height MAX W(W)

Feet Braldwood unit I Cycle 10 0.00 10000 0.20 10000 Figure 26.2.b OAO 10000 o.Wo 10000 Summary of W(Z) Function at s000 MWD/MTU 0.80 1 0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 10000 1.20 1 0000 1.40 1 0000 1.60 100000 1 35 1.30 11942 2.00 11785 2.20 11588 2.40 11425 2.60 1 w8 2.80 1 1229 3.00 11194 3.10 11141 1 30 3.40 11132 3.60, 11109 3.80 11107 4.00 11103 4.20 11070 4.40 11046 4.60 11042 4.80 11008 1 25 5.00 1 0974 5.20 10928

  • 5-.40 1 0883 5.60 10821 z

3.80 1 0887 0 6.00 10944 P 6.20 11100 Z 120 6.40 11267 U.

6.60 11434 6.80 11582 7.00 11715 7.20 1 1860 7.40 11989 7.60 12088 7.8O 12182 115 8.0O 12258 3.20 12341 3.4o 12467 8.60 12563 88O0 12666 9.00 12762 9.20 12851 9.40 12996 110 9.60 13128 9.30 13259 LO.00 13363 10.10 13452 10.8o 10000 10.60 10000 10.30 10000 11.00 10000 105 L 11.20 10000 000 200 400 600 800 1000 1200 11.A0 10000 11.60 10000 CORE HEIGHT (FEET) 11.30 10000 12.00 10000

TODI NFMO100083 Seq 4 Page 10 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 1 CYCLE 10 Height MAX W(Z)

Feet Braidwood Unit 1 Cycle 10 0.00 10000 0.20 10000 Figure 2.6.2.C 0.4O 0000 0.60 1 0O00 Summary of W(Z) Function at 14000 MWD/MTU 0.80 10000 (Top and Bottom 1S% Excluded per WCAP-10116) 1.00 10000 1.20 10000 1.40 1100O0 1.60 10000 1 35 1.80 1 2980 2.00 12810 2.20 12500 2.40 12290 2.60 1 2179 2.80 12113 3.00 12033 3.20 1 1932 1 30 3.40 11841 3.60 1 1726 3.80 1 1620 4.0 11586 4.20 .11538 4.4 1 1490 4.60 1 1406 4.80 1 1335 1 25 5.00 1 1259 5.20 11168 SA0 1.1094 5.60 11109 z

5.80 1 1233 2 6.00 11372 6.20 11506 Z:120 6.40 11618 U. -Olt 6.60 11713

. 1787 7.00 11844 7.20 11868 7.40 11914 7.60 11952 7.80 " 1971 115 6.30 11944 3.10 11885 31 1830 8.60 11736 8.30 11683 20 1 1639 S.L0 11644 9.40 11674 110 9.0 11677 9.80 1 1720 10.00 11980 10.20 12245 10.40 10000 10.60 10000 10.80 10000 11.00 10000 I fl 11.10 10000 000 200 400 600 800 1000 1200 11.40 10000 11.60 10000 CORE HEIGHT (FEET) 11.30 10000 12.00 10000

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-- -- 4 --- - ,- - - -

8 44 8

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- - - - -4.- & - 4. 4. - .A 4. - 4. A - - - .L- J - A - - .. 1 L- A - .1. - - I. - .1. -

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TODI NFMO100083 Seq 4 Page 12 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 1 CYCLE 10 Table 2 6 2 Fq Margin Decreases in Excess of 2% per 31 EFPD Cycle Burnup Max % Decrease (MWD/MTU) in Fq Margin 665 2.00 837 2.19 1008 3.19 1180 4.14 1351 4.99 1523 5.72 1695 6.13 1866 5.93 2038 5.59 2210 5.14 2381 4.63 2553 4.11 2724 3.63 2896 3.23 3068 2.91 3239 2.66 3411 2.45 3583 2.27 3754 2.08 3926 2.00 13365 2.00 13537 2.08 13708 2.27 13880 2.43 14052 2.55 14223 2.62 14395 2.64 14567 2.61 14738 2.53 14910 2.40 15081 2.24 15253 2.06 15425 2.00 Note All cycle burnups outside the range of the table shall use a 2% decrease in Fq margin for compliance with the 3 2 1 2 Surveillance Requirements Linear interpolation is adequate for intermediate cycle burnups

TODI NFMO100083 Seq 4 Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 27 Nuclear Enthalpy Rise Hot Channel Factor (FNa^. (LCO 3 2 2) 27 1 FN < Fl+,[1 0 + PF,(1 0- P)]

where P = the ratio of THERMAL POWER to RATED THERMAL POWER FRHTP 1 70 PFAH =0 3 272 Uncertainty when PDMS is inoperable The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FallNN shall be calculated by the following formula UF. = UFAHm where UFAm = Base FNH measurement uncertainty = 1 04 273 PDMS Alarms FN Warning Setpoint > 2% of FN HMargin F NAi Alarm Setpoint >0% of FNAH Margin 28 AXIAL FLUX DIFFERENCE (AFD) (LCO 3 2 3) 28 1 When PDMS is Inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2 8 1 or the latest valid PDMS Surveillance Report, whichever is more conservative 2 82 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable 29 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3 2 5) 291 DNBRAPsL >21536 The Axial Power Shape Limiting DNBR (DNBRAPsL) is applicable with THERMAL POWER

Ž>50% RTP when PDMS is OPERABLE 292 PDMS Alarms DNBR Warning Setpoint >_2% of DNBR Margin DNBR Alarm Setpoint Ž 0% of DNBR Margin

TODI NFMO100083 Seq 4 Page 14 of 17 CORE OPERATING LIMITS REPORT (cOLR) for BRAIDWOOD UNIT 1 CYCLE 10 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power

TODI NFMO100083 Seq 4 Page 15 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 1 CYCLE 10 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 / OF 2 10 3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0 00181 / psig 2 10 4 The nominal Tang 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 shall be equal to 8 sec 2 10 7 The measured reactor vessel AT lead/lag time constant 2 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 r4 shall be equal to 33 sec 2 10 10 The measured reactor vessel average temperature lead/lag time constant r5 shall be equal to 4 sec 2 10 11 The measured reactor vessel average temperature lag time constant T shall be less than or equal to 2 sec 2 10 12 The f, (Al) "positive" breakpoint shall be +10% Al 2 10 13 The f, (Al) "negative" breakpoint shall be -18% Al 2 10 14 The f, (Al) "positive" slope shall be +3 47% I % Al 2 10 15 The f, (Al) "negative" slope shall be -2 61% / % Al

TODI NFMO100083 Seq 4 Page 16 of 17 CORE OPERATING LIMITS REPORT (cOLR) for BRAIDWOOD UNIT 1 CYCLE 10 2 11 Reactor Trip System (RTS) Instrumentation (LCO 3 3 1) - Overpower AT Setpoint Parameter Values 2 111 The Overpower AT reactor trip setpoint 1(4 shall be equal to 1 072 2 11 2 The Overpower AT reactor trip setpoint T3vg rate/lag coefficient K5 shall be equal to 0 02 / OF for increasing Tavg 2 11 3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Kr shall be equal to 0 / OF for decreasing Tavg 2 11 4 The Overpower AT reactor trip setpoint Tavg heatup coefficient Kr shall be equal to 0 00245 /1 F when T > T" 2 11 5 The Overpower AT reactor trip setpoint Tayg heatup coefficient K%6 shall be equal to 0I/F when T < T" 2 11 6 The nominal Tayg 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 r, 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 r3 shall be less than or equal to 2 sec 2 1110 The measured reactor vessel average temperature lag time constant T shall be less than or equal to 2 sec 2 11 11 The measured reactor vessel average temperature rate/lag time constant C7 shall be equal to 10 sec 2 1112 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 1114 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

TODI NFMO100083 Seq 4 Page 17 of 17 CORE OPERATING LIMITS REPORT (cOLR) for BRAIDWOOD UNIT 1 CYCLE 10 2 12 Reactor Coolant System (RCS) Pressure, Temoerature. 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 380,900 gpm 2 13 Boron Concentration 2 13 1 The refueling boron concentration shall be greater than or equal to 1670 ppm (LCO 3 9 1) 2 13 2 The Reactor Coolant System boron concentration, with all shutdown and control rods fully withdrawn, shall be greater than or equal to 1722 ppm prior to initial criticality of Cycle 10, or greater than or equal to 1972 ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3 1 g and 3 1 k2)

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