ML030990421

Core Operating Limits Report, Cycle 10 Sequence Number 5

ML030990421
Person / Time
Site:	Braidwood
Issue date:	03/31/2003
From:	Vonsuskil J Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW030025
Download: ML030990421 (19)

Text

Exelkn.

Exelon Generation Company, LLC www exeloncorp corn Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel 815-417-2000 March 31, 2003 BW030025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 10 Sequence Number 5 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 10 Sequence Number 5, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)". This revision of the COLR was recently implemented and revises item 2.5.4, item 2.6.2 and corresponding Figures 2.6.2.a through 2.6.2.d, and item 2.13.2.

These changes include: 1) deleting a control bank park position that will not be used, 2) updating W(z) data by providing data for burnups of 22,000, 23,000 and 25,000 MWD/MTU, and 3) editorial changes.

If you have any questions regarding this matter, please contact Mr. Scott Butler, Acting Regulatory Assurance Manager at (815) 417-3540.

Respectfully, es D. von Suskil e Vice President Braidwood Station

Attachment:

Core Operating Limits Report, Braidwood Unit 1 Cycle 10 Sequence Number 5 cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station

ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 1, Cycle 10, Sequence Number 5

NUCLEAR FUELS DEPARTMENT TRANSMITTAL OF DESIGN INFORMATION 3 SAFETY RELATED Originating Organization l TODI No. NFM0100083 o NON-SAFETY RELATED E Nuclear Fuels Seq No. 5 o REGULATORY RELATED E Otherlspecify) l Page I of 17 Station Braidwood Unit I Cycle 10 Generic To Lonnie K. Kepley - Bratdvkood Subject Braidvood Unit I Cycle 10 Core Operating Limits Report in ITS Format and W(z) Function Rob Lee 03/14/03 Preparer Preparer's Signature Date Annie Along & g) 03/14/03 Reviewer Resle 's Sienature 1 Date Ted Lindholm (for Bob Tsai) / - 03/14/03 NF Supervisor NF Supervi(or's Signature Date Status of Information ED Verified O Unverified 0 Engineering Judgement Method and Schedule of Venficatton for Unverified TODIs:

Description of Information:

Attachment I is the Braidwood Unit I Cycle 10 Core Operating Limits Report (COLR) Sequence 5 in the ITS format and W(z) function.

Sequence 5 of this TODI supersedes Sequence 4.

Purpose of Information:

The attached Core Operating Limits Report (COLR) for Braidwood Station Unit I 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 (as descnbed in letter NF-MW-03-106, dated 3/11/03)

- Item 2.5 4 of the COLR is being revised to remove the last line of the table which reads 231 vs. 116"

- Item 2.6 2 of the COLR and the corresponding Figurcs 2 6.2.a through 2.6 2 d are being revised with newly updated W(z) data

- Item 2.13.2 of the COLR is being revised for updated wording 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 pontion to the Nuclear Regulatory Commission pursuant to Technical Specification 5 6 5. Please provide NF tRob Lee) with a copy of Braidwood Station's completed plant review and COLR submittal to the NRC.

Source of Information I. Westinghouse Ltr 01 -CB-G-15 1. "Braidwood Unit I Cycle 10 COLR Data". dated 08/28/01.

2. Westinghouse Lir 01-CB-G-1 53. "Braidwood Unit I Cycle 10 COLR Revision I, dated 08/31/01.

3. TODI NFMOI 00062, Revision I, -BR I C10 Reload Design Initiation", dated 06/12101.

4. NFS PNDCN 00-003. Res 0. -Evaluation of SPIL Using 224 Steps Rod Withdrawn as Definition of ARO"; dated 05/11/00

5. Westinghouse Lir 01 -CB-G-112. "Braiduood I Cycle 10 BEACON DMM Model Delivery", dated 07/2701 .

6. Westinghouse Lir 01 -CB-G- 155, "Braidwood Unit I Cycle I0 Boron Concentration for Startup Physics Testing", dated 09/07/01

7. Westinghouse Lir NF-CB-03-62/CAC-03-65. "Braidwood Unit I Cycle 10 Revised W(z) Factors." dated 03/13/03.

Supplemental Distribution L S Dworalkowski (BR)

SupplementalL S DrlkDitibto (_R

TOD] NFM0100083 Seq. 5 Pa-e 2 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 1.0 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 2.1.1 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 (Fo(Z))

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

LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3 2.5 Departure from Nucleate Boiling Ratio (DNBR)

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

LCO 3 4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below:

TRM TLCO 3.1.b Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1 .h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff 2 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 NFM0100083 Seq. 5 Pane 3 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I 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 2250 psia Lj)

<)7.,

6 4D W

L_

iE!

Q)

Q>

620 600 580 2

Fraction of Nominol Power Figure 2.1.1: Reactor Core Limits

TODI NFM0100083 Seq 5 Page4 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I0 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 11. 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.

222 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).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3) -

The Moderator Temperature Coefficient (MTC) limits are:

2 3.1 The BOUARO/HZP-MTC upper limit shall be +2.14 x 10- Ak/k/CF 2 32 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 104 Ak/k/CF 233 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/CF.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4 3 x 104 Ak/k/CF.

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 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 the following overlap limits as a function of park position.

Park Position (step) Overlap Limit (step) 225 l 110 226 111 227 . 112 228 113

• 229 1 114

TOD] NFM01000S3 Seq. 5 Pare 5 of 17 CORE OPERATING LIMITS REPORT (COLR) ior BR AIDWOOD UNIT I CYCLE 10 Figure 25.1:

Contrdol Bank Insertion Lnits Versus Percent Rated Them-ld Poaer 224 VP/6. 224) 24)

(77O/P, 220 200 180 4- 160 i001(100,161)

D 0.

140 U,

la 4-120 0 100 m

'V c

C-l 80 0

60 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percert)

TOD] NFMO0100083 Seq. 5 Page 6 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 10 26 Heat Flux Hot Channel Factor (Fofgfl (LCO 3.2.1) 2.6.1 Fo (Z) -5 xK(Z) forP c0.5 0.5 F RTP F0 (Z) <- xK(Z) forP>O.5

- P. .e where: P = the ratio of THERMAL POWER to RATED THERMAL POWER RIPT Fo P = 2.60 K(Z) 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 normal operation W(Z) values have been determined at burnups of 20000, 22000, 23000, and 25000 MWD/MTU to support operation after 22000 MWDIMTU.

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 FWolz) 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

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 UFO = Up

• U, where:

UQU = Base FO0 measurement uncertainty = 1 05 when PDMS is inoperable.

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 2 0% of F0 {Z) Margin

TOD] NFM0100083 Seq. 5 Pace 7 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I)

Figure 2.6.1: K(Z) - Normalized F0(Z) as a Function of Core Height 1.1

- I - (6.01 0)Il1i 1

(12.10 924) 0.9 0.8 FZ 0.7 U-I I I I I 1-I ax N

06 IIlI I I T E

z a 05 I__

I I I9

-- LOCA Limiting Y 04 I Envelope I 0.3

. _ lI 0.2

.~ __I______

0.1 0

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

TOD] NFM0100083 Seq. 5 Pare 8 of 17 CORE OPERATING LIMITS REPORT icoi R)for BRAIDWOOD UNIT I CYCLE 10 Hw Fhmwc)

F49 Bmkr%=wutkt 1Cv 10 Om 10000 am I o00 Fgze2Ln am kts I ooo am 1 0000 I 0(00 100000 I oooo I ohoo I1 0000 onoO 1.35 I=

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LW LW sm 11874 2

Lm

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LA-1 2521 1 2568 7W 132586 am 7W 12.245 7D 1.2504 t.t . ,

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TOD) NFMO100083 Seq. 5 Pare 9 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 10 Ht PWX waJ m0dLk*it Ce 10 Fa I 0000 am 1 0000 FbMe22lb I 0000 StumtydWW hNtwckn t41ADAM CLW I (X) flwctrW MOMS% E-WzlepOWCW-1a I t0O cm I 20(0 20 I (22 l1W I (irg) 1 35 tm 122,4 VW 2W 2m I2011 2LW I 192, 26D lW I j,14 1 30 310 I I648 1 NOw 9

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• 9 9 1 2545 __

7AO

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7.0 1 2504 1 2415 9 7M 1 2315 115 ILW 1 2197 am RAO 1 2029 11I62 _________ 9 11666 1 1490 SW 11329 sm am 11214 90 11300 1'10 11760 1 2160 1 2510 3W 1 2870 (00)0 10000 11C 10000 la 11.6D I 0000 105

'tin I 0000 000 2 00 4 00 6 00 8 00 1000 1200 I 0000 11110 CORE HEIGHT (FEET) 10000 11W I t)O rim 10000

TOD] NFMOIOOOS3 Seq. 5 Page IOof 17 CORE OPERATING LIMITS REPORT (COLR) for BRAlDWOOD UNIT I CYCLE 10 He tWX WQ)

Fe mdiU=Lk*l Cpe1O am 1 0000 am 1 0000 romF Lc am I 0000 1(0000 SumnvdW<t)WFt1K3 t2 M9MWD*

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10000 I.W 1 35 -

VW I2'78 LW 2W I2217 LW 2m 12121' -- i--- *1 4 I 4 2w I 1929 2W 1 30 -t ,-4-I-4 111634 LW mm mm Im I 1669 eLW SW 4w I 1553 SW I1607 1 25 1 1659 so 11714 117319 5" I 2Ih53 2

SW I2059 SW 1 2214 740 12149 1 20 I 4 I1 16h46 2455 1.2521 4 4 1 2568 SW 1 2586 FLW I 2h45 am I12504 am 12415 0 La 7= 1 15 I 2197 I 2029 I 1862 S0 am 1 DODO I1 25h6 1490 U7 am 11329 7AD 11214 113100 1 10 11760 I2160 1 2530 12870 10I 0000 m0 113000 1 05 I I I I ---I lU.

0c 0 200 400 600 800 1000 1200 1140 I 0000 I0000 CORE HEIGHT (FEE 11W

TOD] NFM0100083 Seq. 5 Pare 1I of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 10 MAXWW}

Newt PM I Woo am Q6D I 00)0 Q0 o0on cm I 0W00 StnIT11y c WM 5ack-It h2MTIJ P

I 00)o Ifcp,ft Bcin 15%/ ENMW pe IWCAtM=

am I o00 oo000 oooo0 1)o0 1 35 2L0 I 2178 1.22;7 tm 2.0 12128 2.00 am 120.3 1 1925 2m 1 I8,I 200 1 17;9 1 16-4

• 30 1 1651 140 1 1700 1 1677 1I669 11644

&W 1 161 __ _ __ . .

1 155; am 11607 1.25

&M 1 16;9 __ ,_.___ _ .

sm 11714 LW 1 1719 LW 11874 z

sm Lw 12099 12214 0 * ~4 12349 6m 12455 L 1.20 am 12S21 KL aS 1 2568 1 2586 7.M 1 2545 _ ___

7.90 12504 7.O 12415

?.0 1 2315 1.15 1 2197 1 2029 89 11862 11666 am 11490 am 11329 11214 gm 11300 1 10 gm 11760 gm 1 2160 1 2530 12870 1 0000 _ _ I _ _ I I_.1 I _ _ I 19A 1 0000 I - + I 4 1 0000 urn 10 10000 1 05 I LW I0000 00 i0 2 00 4 00 6 00 8&00 1000 1200 IDo00 IDooo CORE HEIGHT (FEET) 1 o0o 12.0 I 0000

TODI NFT4OlOOO8 3 Seq. 5 Page 12 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I 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.

TOD] NFNMOIO0083 Seq 5 Pane 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 10 2.7 Nuclear Enthalpv Rise Hot Channel Factor (F k (LCO 3.2.2) 2.7.1 FAH < FA'H'[1.0 + PFH(l 0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FLH = 1 70 PFH = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFaH to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FIHN shall be calculated by the following formula:

UFaH = UFAHm where:

UFj,,, = Base F ,H measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNAH Warning Setpoint 2 2% of FNAH Margin FN H Alarm Setpoint 2 0% of FN 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 Figure 2.8.1 or the latest valid POMS Surveillance Report, whichever is more conservative.

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 2 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER 2 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms - _

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

TOD] NFM0100083 Seq 5 Pa-e 14 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWVOOD UNIT I CYCLE 10 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Adal Flux Difference Units With PDMS Inoperale M

50 .

120 -

10).. 0i-O 1002) -J3 o!s

Th 4 II i'

-. ,C -20. 30 50400-0100 102345 AALU6J FLUX)DI FJn (O/14 f

TOD] NFM0100083 Seq. 5 Pane 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I 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 Tag coefficient K2 shall be equal to 0 0297 / 'F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0 00181/ psig 2.10 4 The nominal T,,, 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 T2 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 t.4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant t5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant t6 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% 1% Al.

2.10 15 The f1 (Al) 'negative' slope shall be -2.61% 1% Al.

TOD] NFMOIOOO83 Seq. 5 Pace 16 of 17 CORE OPERATING LIMITS REPORT COLR) i for BRAIDWOOD UNIT I CYCLE 10 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 K4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip selpoint Tvg rate/lag coefficient K5 shall be equal to 0.02 / OF for increasing T avg 2.11.3 The Overpower AT reactor trip setpoint T,,,rate/lag coefficient K5 shall be equal to 0 I F for decreasing Ta..

2.11.4 The Overpower AT reactor trip setpoint Tag heatup coefficient K(6 shall be equal to 0.00245 / IF when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0/ IF when T T'.

2.11.6 The nominal TBV9 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 Trshall be equal to 8 sec.

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

2.11.9 The measured reactor vessel AT lag time constant T3 shall be less than or equal to 2 sec.

2 11.10 The measured reactor vessel average temperature lag time constant t6 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 (AI) '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.

TOD) NF?10I10f)83 Seq. 5 Pate 17 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE IO 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 (Tvg) 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 1670 ppm (LCO 391) 2.13.2 To maintain keff < 0 987 with all shutdown and control rods fully withdrawn in MODES 3,4, or 5 (TRM 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:

a) 1722 ppm prior to initial criticality.

b) 1972 ppm at all other times in core life.