Braidwood Station, Units 1 and 2, Core Operating Limits ... · Attachment 2: Core Operating Limits Report for Braidwood Unit 2 Cycle 10 (CAC-02-48, Revision 5) cc: Regional Administrator

xe kn.MExelon Generation Company, LLC www.exeloncorp.com NucleaTBraidwood Station35100 South Rt 53, Suite 84Braceville, IL 60407-9619Tel. 815-417-2000

August 1, 2003BW030063

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001

Braidwood Station, Units 1 and 2Facility Operating License Nos. NPF-72 and NPF-77NRC Docket Nos. STN 50-456 and STN 50-457

Subject: Core Operating Limits Report (COLR) Revisions

The purpose of this letter is to transmit revisions to the Braidwood Station, Unit 1 COLRand the Braidwood Station, Unit 2 COLR in accordance with Technical Specification 5.6.5, "CoreOperating Limits Report (COLR)." These revisions of the COLR were recently implemented toincrease the COLR limit for the reactor coolant system (RCS) total flow rate from greater than orequal to 380,900 gallons per minute (gpm) to greater than or equal to 386,000 gpm. The RCS totalflow rate is being increased to address a core design constraint that 0% of rods experiencedeparture from nucleate boiling for the Locked Rotor event.

If you have any questions regarding this matter, please contact Ms. Kelly Root, RegulatoryAssurance Manager, at (815) 417-2800.

Respectfully,

Micha I J. PacilioSite Vice PresidentBraidwood Station

Attachments:Attachment 1: Core Operating Limits Report for Braidwood Unit 1 Cycle 11

(CAD-03-89, Revision 1)Attachment 2: Core Operating Limits Report for Braidwood Unit 2 Cycle 10

(CAC-02-48, Revision 5)

cc: Regional Administrator - NRC Region IIINRC Senior Resident Inspector - Braidwood Station

4u1

bcc: NRC Project Manager, NRR - Braidwood StationOffice of Nuclear Facility Safety - IDNSSite Vice President - Braidwood StationRegulatory Assurance Manager - Braidwood StationDirector - Licensing, Mid-west Regional Operating GroupManager - Licensing, Braidwood and Byron StationsNuclear Licensing Administrator - Braidwood StationNuclear Fuel Management - Robert LeeExelon Document Control Desk Licensing (Hard Copy)Exelon Document Control Desk Licensing (Electronic Copy)

ATTACHMENT I

Core Operating Limits Report

for

Braidwood Unit 1 Cycle 11

CAD-03-89, Rev. I

CORE OPERATING LIMITS REPORT (COLR)

FOR

BRAIDWOOD UNIT 1 CYCLE 11

Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP

CAD-03-89, Rev. I Page 2 of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II

Applicable for PDMS Inoperable AFD Limits from -18% to + 10% at 100% RTP

1.0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report (COLR) for Braidwood Station Unit I Cycle 11 has beenprepared 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 Reor Core Safety Limits (SLs)

LCO 3.1.1 Shutdown Margin (SDM)

LCO 3.1.3 Moderator Temperature Coefficient fMTC)

LCO 3.1.4 Rod Group Alignment Limits

LCO 3.1.5 Shutdown Bank Insertion ULmits

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,)

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 Departurefrom Nucleate Boiling (DNB) Limits

LCO 3.9.1 Boron Concentration

The portions of the Techrucal Requirements Manual affected by this report are listed below-.

TRM TLCO 3.1.b Boration Flow Paths - Operating

TAM 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 keNl 21.0

TRM TLCO 3.1.1 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)

CAD-03-89, Rev. I Page 3 of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I


2.0 OPERATING LIMITS

The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in thefollowing subsections. These limits are applicable for the entire cycle unless otherwise identified.These limits have been developed using the NRC-approved methodologies specified in TechnicalSpecification 5.6.5.

2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1)

2.1.1 In Modes I and 2, the combination of Thermal Power, Reactor-Coolant System(RCS) highest loop average temperature, and pressurizer pressure shall notexceed the lirmits specified In Figure 2.1.1.

680

660

La.

UP

0, 640a,I-

QC-Ea,> 620

U)WC11

600

589

271ps.

2250 psGa

\00 \_i

0 .2 -4 .6 8~~~~~~ 1.22I

Froction of Nominal Power

Figure 2.1.1:. Reactor Core Limits

CAD-03-89, Rev. IPage 4 of 17

CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE IIApplicable for PDMS Inoperable APD Limits from -18% to +10% at I100% RTP

2.2 SHUTDOWN MARGIN (SDM)

The SDM lirnit 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, 3.1.1, 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% Ek/k (LCO 3.1.1, LCO 3.3.9; TRMTLCOs 3.1.1 and 3.1.).

2.3 Moderator Ternmerature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOLUARO/HZP-MTC upper limit shall be +1.185 x l0' bkk/PF. -

2.32 The EOLUARO/HFP-MTC bwer limit shall be -4.6 x 10 4Ak/kPF.

2.3.3 The EOUAR01HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104Ak F.

2.3.4 The EOLUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10, AkIkF.

where: BOL stands for Beginning of Cycle LifeARO stands for All Rods OutHZP stands for Hot Zero Thermal PowerEOL stands for End of Cycle LifeHFP stands for Hot Full Thermal Power

2A Shutdown Bank Insertion Lirnits (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 belimited 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 greaterthan or equal to 224 steps.

2.5.3 The control banks shall be operated In sequence by withdrawal of Bank A, BankB, Bank C and Bank D. The control banks shall be sequenced in reverse orderupon insertion.

2.5.4 Each control bank not fully withdrawn from the core shall be operated with thefollowing overlap limits as a function of park position:

Park Position (step) Overlap Limit (step)225 110226 - 111227 112228 113229 114


Applicable for PDMS Inoperable AFD Limits from -I 8% to +10% at 100% RTP

hgure 2.S1:Co" Bank Inseaon UmtsVersus Percent Fted Thenm

Ila

0

100-

.x

0

(lMEq 161)

0 10 20 30 40 5D 69

wwwPo (Pernt)

70 80 90 100



2.6 Heat Flux Hot Channel Factor (Fn(Z)) (LCO 3.2.1)

2.6.1

FRTPFQ(Z)< xK x (Z) forP<0.5

0.5

FQ(Z) S-- -xK(Z) forP >0.5

where: P = the ratio of THERMAL POWER lo RATED THERMAL POWER

Fp = 2.60

K(Z) Is provided In Figure 2.6.1.

2.6.2 W(Z) Values:

a) When PDMS is OPERABLE. WM =1.00000 for all axial points.

b) When PDMS is Inoperable, W(Z is provided in Figures 2.6.2.a through2.6.2.d.

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

Table 2.6.2 shows the Fco(z) penalty factors that are greater than 2% per 31Effective Full Power Days. These values shall be used to increase the FWo(z) asper Surveillance Requirement 3.2.1.2. A 2%A penalty factor shall be used at allcycle bumups that are outside the range of Table 2.6.2.

2.6.3 Uncertainty:

The uncertainty, UFO, lo be applied o. the Heat Flux Hot Channel Factor Fo(Z)shall be alculated by the following formula

UIe = UV. *U,

where:

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable.(U. Is defined by PDMS when operable.)

U. = Engineering uncertainty faclor = 1.03

2.6.4 PDMS Alarms:

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

CAD-03*89, Rev. I Page 7 of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II


Figure 2.6;1K(Z) - Normalized F0(Z) as.a Function of Core Height

1.1

1

0.9

(0.011.0) |(6.0 1.0)t,, -r-I.-.-I -I I I -II I ~~~~~~~~~(12.(10.924)

0

N

-a

0.8 - a

0.7 …

0.6 _ - - - -_

0.5a

0___LOCA Linifing0.4 - _ _ - Envel

0.3 - - a a - -

O2…

0.1 _

0O

0 1 2 3 4 5 6 7 8 9 10 11 12

BOTTOM Core Height (f)T TOP

CAD-03-89, Rev. 1 Page 8 of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II

Applicable for PDMS Inoperable Al D Limits from -18% o +10% at J00% RTP


HeightFeel0.00200.40.600.801.001.20lAO1.601.801.120022D2402602.80&OD3.003.203.603A0

4.004204.404.604.80

520

5.165.806.006206.406.606.807.CO7.2D7.407.607.J0

8.20

8.608.8D9.0D9.209.409.609.8010.0010.2010.4010.6010.80Iuoop12011.4011.6011.8012.0D

MAX W(ZI

1.0000la001t0w

1U000

3.2450

321333

L.2027

1.18361.1321

3.17301.1.3650

1.1345

1.12481.1142140263.09861.09831.30963.13691.12631.13391.1416

1.14S8

3.16201.1739

.1.38941.1971

1.2024

32102

1211

12317

1.0000

1.0=0

l.00003.0000

StokwAoxd hUr I Cycle I1I

F~g'e 2.62A

Sumaroy cI W(7) Function of 150 MWAD/M11J(Top ard 1of1am 15% Ex'ck3ded pet WCAP-10216)

1.30

125

z

Z 1.20

1.15

1.10

1.05

I*T'

0.00 2.00 4.00 6.00 8.C

CORE HEIGHT (FEET)

.0 10.00 12.0O

.

CAD-03-89, Rev. 1 Page 9of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE I J



Heigh1Feel

0200.400.60OWS

12D

1.601.802.O0Z2.222D2602.803m

3.403A03804.004.204.404.604.805m5420

5.05S.6.006.206.406.6068.7.007207.407.607.808.008.208.408.60a-so9.009.209.409.609.800.00

10.2010.4010.6010.801101120

34AO116011.8012.00

MAA.XW(Z)

3.0000l.0003.0000L.00001.0000o3.00003l0003I000)AM0131131US9113263412413132273320031.1934131f443.37603.16843.14083.35153.14121.33133.11901.10793.09871.09313.0953.0991.13W3.11023.33433.32053.13421.34591.15763.16983.31811.19331.20311.21211.21713.2233.22873.2491.24455.2630127501.2S812041.29701.30301.00003.00003.0001.0003.00001.00003.00003.00001.0000

N~dctwood" UIt 1cycle Ii

Flgwe 262.b

Surnmory d W(D Function at 6000 NMWMIU(Top and Bottom 15% Eaick~ed pef WCAP-102 16)

I I I I I I I I I

I:I

t I

CAD-03-89, Rev. I Page IOof 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11

Applicable for PDMS Inoperable AFD Limits from -1 8% to +10% at 100% RTP

Applicable for PDMS Inoperable AFD Umits from -18% to +10% at 100% RTP

Heightfeel0-000.200>40

OLID

140

1.6011802002202A026O2.80U3.3203403.603.80

4204AO4.604.80

£405205.43

6800

6.206406.606.80

7.007207A07.67.08.08.208.A08.606809m9209.49.609.8010.0102010.4010.010.8011.O11.20114011.60MO.80

12.00

MAX W(Z)

1.0000

10001.00001.0000

1L000013009SAm93.0000

33096

1.27691.26511.25121.24221.23211201.20841.202SLIM1.1,9021.11201317341.16391.15443.3440'.340,11,4011.140t1.34521.35383.17043.33DD1.13653.319131.1940

3.39273.195

3.379631.6971.16Z7

L3627t~577

1.15611.15611.15371.15241.1497

1.20S01.23601.0000

9M002z003.00001.0000

3.00001.0000

Brok1w~ood Unil I Cycle I I

I tIw 2.6.2.c

&owrmory of W(Z Fumcton ot 1400 MWO/MI(IoP mod Botom 15% Enckoded pmtWCAP-10216)

1 I

I *1

I I1

CAD-03-89, Rev. I Pagc I I of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I

Applicable for PDMS Inoperable AFD Limils from -1 8% to + 109' at 100% RTP


HeightFee1100Q20

0.60Q80I001201.40leolJO

120z402,602.803.0D3.20.3.403.603.80too4.204.404.604.80&aOD6.20A40&60

.806.006.206AO6.60b.W07.007.20

_7.607.808.008.20

9.009.209.409.609.8010.0010.2010.4010.6010.8011.0011.2011.4011.6011.012.00

3.0000

3.0000

IW000

J.000

1.25901.2390

1.20203.19)01.1910

1.1892

1.1871I.IW51.202381.208932309321251.2110

.2-2~01-23341.24311.25011.2545I25631.25123.24911.24301.23111.21923.20613.1914LIMSf3.36253.36441.16401.13131.17021.21101.249032221.31423.00003.0003.000ID=03.600I.0OD3.600001.00003.0000

1#Oldoodr 1. CyCle 1I

Figme 2.62,d

Survviory of W(Z) Fun~ction of 20000 MWD/MUl(top ond Bottom 15% Exckxcied pet WCAP..10216)

1.3s

1.30

1.25

z

0Z 1.20

.R

1.15

I4

4LH1

I - J. .4-5 J..J....4 I � 4 � 444..-4 .-i ..I-.-J..

I Ii1 -i-rii-i rrrv iri v i- ii --LI

1.10

- -I. .-

I I1.051

O.CDO 2.00 4.00 6.00 8.00 tO.00 12.O0

CORE HEIGHT (FEET)


Applicable for PDMS Inoperable AFD Limits from -18% to 1J0% at 100% RTI


Table 2.6.2

- Penalty Factors in Excess of 2% per 31 EFPD

Cycle Bumup Penalty Factor- F'0 (z)(MWD/MTU) )

495 2.00839 44A81012 5.661184 6.581356 7.151529 7.201701 6.971874 6A92046 5.822218 5.102563 3.792735 3.352908 3.103080 3.013597 3.163769 3.093942 2.864114 2.474286 2.014459 2.00

Notes:

Linear interpolation Is adequate for Intermediate cycle bumups.

All cycle bumups outside the range of the table shall use a 2% penalty factor for cormpriance withthe 3.2.1.2 Surveillance Requirements.

CAD403689: Rev. IPage 13 of 17

CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE IIApplicable forPDMS Inoperabie AFD Limits from -18% to +1O% at I00% RTP

2.7 Nuclear EnthalPy Rise Hot Channel Factor (ETaH) (LCO 3.2.2)

2.7.1 F^H S FZTP[ 1 .0 + PFX,,(1.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWERFZ' = 1.70PFK = 0.3

2.7.2 Uncertainty when PDMS Is inoperable

The uncertainty, UF&H, to be applied to the Nuclear Enthalpy Rise Hot ChannelFactor FHN shall be calculated by the following formula:

UFW4 = UF

where:

UxF~= Base F%4 measurement uncertainty =1.04

2.7.3 PDMS Alarms:

F'4H Warning Setpoint a2% dof Fj MarginF ' Alarm Setpoint 2 0% of FNaH Margin

2.8 Axial Flux Difference (AFD) (LCO 32.3)

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

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

2.9 Deparlure from Nucleate Boilino Ratio (DNBR) (LCO 3.2.5)

2.9.1 DNBRApsL 1.536

The Axdal Power Shape Umiting DNBR (DNBRpsL) Is applicable with THERMALPOWER > 50%/* RTP when PDMS Is OPERABLE.

2.9.2 PDMS Alarms:

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

CAD-03-89, Rev. I Page 14 of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I

Applicable for PDMS Inoperable AFD limits from -1 8% to + 10% at 100% RTP

Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power

Applicable for PDMS Inoperable AFD Umits from -18% to +10% at 100% RTP

Mal FIlux Uffferermx UnitsvWth

-PONVS Inoperbl

120

I 6(

020000--.180

W 0

W 0

-i~p allr-- oep

-50 -40 -30 -20 -10 0 10 20 30 40 50A)XX fUX OEffERB0i4(0/4

CA U-l3-bsy. Kev. I Page 15 of 17CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11

Applicable for PDMS Inoperable AFD Linits from -18% to +10% at 100% RTP

2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT SetpointParameter Values

2.10.1 The Overtemperature AT reactor trip selpoint K, shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpolnt T, coefficient K2 shall be equalto 0.0297/ eF.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient 43 shall beequal to 0.00181 / psig.

2.10.4 The nominal T.,at RTP (indicated) r shall be less than or equal to 588.0 "F.

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

2.10.6 The measured reactor vessel AT leadtlag lime constant sr shall be equal to 8sec.

2.10.7 The measured reactor vessel AT lead/lag time constant a2 shall be equal to 3se.

2.10.8 The measured reactor vessel AT lag time constant ? 3 shall be less than orequal to 2 seec

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

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

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

2.10.12 The 1, (Al) "positive" breakpoint shall be +10/e AI.

2.10.13 The It (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 (A negative slope shall be -2.61% 1% Al.

CAD-03-89. Rev. I Page 16 of 17CORE OPERATING IUMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11


2.11 Reactor Trip System (RTS) InsIrumentation (LCO 3.3.1) -Overpower AT SetpointParameter Values

2.11.1 The Overpower AT reactor trip selpoint K4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint T9 rate/lag coefficient Ks shall beequal to 0.02 / OF for increasing T...

2.11.3 The Overpower AT reactor trip setpoint T,, rate/lag coefficient K5 shall beequal to 0 'F for decreasing T, ,

2.11.4 The Overpower AT reactor trip setpolnt Tao heatup coefficient KG shall be equalto 0.00245 / °F when T > To.

2.11.5 The Overpower AT reactor trip setpolnt T,, heatup coefficient Ki shall be equalto0/'FwhenTSTo.

2.11.6 The nominal T, at RTP (indicated) T" shall be less than or equal to 588.0 eF2.11.7 The measured reactor vessel AT lead/lag time constant so shall be equal to 8

sec.

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

2.11.9 The measured reactor vessel AT lag time constant r3 shall be less than orequal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant -re shafl beless than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant a7 -shall be equal to 10 sec.

2.11.12 The f2 tAl) positive' breakpoint shall be 0 for all Al.

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

2.11.14 The f2 (Al) positivde slope shall be 0 for aft Al.

2.11.15 The f2 (Al) "negativeW slope shall be 0 for all Al.

CAD-03-89, Rev. IPage 17 of 17

CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I- Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP

2.12 Reactor Coolant System (RCS) Pressure, Temperature. and Flow Departure fromNucleate Boilina (DNB) Limits (LCO 3A.1)

2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psIg.

2.12.2 The RCS average temperature (T.) 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 1701 ppm(LCO 3.9.1).

2.132 To maintain keff 5 0.987 with ell shutdown and control rods fully withdrawn InMODES 3.4, or 5 (TRM 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), theReactor Coolant System boron concentration shall be greater than or equal to:

a) 1733 ppm prior to Initial criticality.b) 1979 ppm at all other times In core life.

ATTACHMENT 1

Core Operating Limits Report

- for

Braidwood Unit 2 Cycle 10

CAC-02-48 Rev. 5 >

CORE OPERATING LIMITS REPORT (COLR)

FOR

BRAIDWOOD UNIT 2 CYCLE 10

CAC-02-48, Rev. 5 PageI of i7

CORE OPERATING LlMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10

1.0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 10 has beenprepared 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 Not Channel Factor (Fo(Z))

LCO 3:2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,.)

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) Instrunentation

LCO 3.3.9 Boron Dilution Protection System (BDPS)

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure fromNucleate 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 >1.0

TRM TLCO 3.1.i Shutdown Margin (SDM) - MODE 5

TRM TLCO 3.1tj Shutdown and Control Rods

TRM TLCO 3-1.k Position Indication System - Shutdown (Special Test Exception)

CAC-02-48 , Rev. 5 Page 2 of 17

CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10

2.0 OPERATING LIMITS

The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in thefollowing subsections. These limits are applicable for the entire cycle unless otherwise identified.These limits have been developed using the NRC-approved methodologies specified in TechnicalSpecification 5.6.5.

2.1 Reactor Core Safety Limits (SLs) (S1 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 shalg notexceed the imits specified in Figure 2.1.1.

Sao

S650

Lj-.

C70i..

0-E.U)

6200

581

247J pmi

Frocdion of lNomiol Power

Figure 2.1.1: Reactor Core Limits

CAC-02-4 8, Rev. 5 Page 3 of 17

CORE OPERATING LIMITS REPORTIcOLR) for BRAJDWOOD UNIT 2 CYCLE 10

2.2 Shutdown Marmin (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%/6 Akfk (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.]).

The SDM limit for MODE 5 is:

2.2.2 SDM shag be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRMTLCOs 3.1.i and 3.1j).

2.3 ModeratorTemperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOIJAROAHZP-MTC upper limit shal be +2.57 x 10r Ak/kIF.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 1 Df Ak/klF.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shag be47 x 1IJ Ak/k/OF.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10 ~ k/k1F.

where: BOL stands for Beginning of Cycle LifeARO stands for All Rods OutHZP stands for Hot Zero Thermal PowerEOL stands for End of Cycle LifeHFP 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 (LC0 3.1.6)

2.5.1 The control banks, with the Bank A greater than or equal to 224 steps, shall belirmied in physical insertion as shown h Figure 2.5.1.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greaterthan or equal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, BankB, Bank C and Bank D. The control banks shag be sequenced in reverse orderupon insertion.

CAC-02-48, Rev. 5

Page 4 of 17

CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE IO

2.5.4 Each control bank not fully withdrawn from the core shall be operated with thefollowing overlap limits as a function of park position:

. . ... . . . _

_Park Position (step)

225226227228229 I

-

Overlap Lnnit (step)t1011i112113114

CAC-V2-48, iKev. > Pagc5 of 17

CORE OPERATINGIUMITSREPORT (COLR)forBRAIDWOODUNIT22 CYCLE 10

:Figre 251::Cor Bank Isrlon Unts Verss Percent PWd Thenal

-Power

224 (nV 22

180C

'Su 18D

CL

a)

0

0

. 0C

0

40-

(1% 161)

0 10 20 30 . 40 SD 6) 70 OD

Relve P w e)

9D 100

CAC-02-48, Yev. -Page 6 of 17

CORE OPERATING LIMITS REPORT (COLA) for BRAIDWOOD UNIT 2 CYCLE 10

2.6 Heat Flux Hot Channel Factor Fool (LCO 3.2.1)

2.6.1

pRTP

FQ(Z)< o-5 xK(Z) forP50.5

FQ(Z) <- Q xK(Z) forP>O.5P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER

FT = 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 Figukes 2.6.2.a through2.6.2.d.

The normal operation W(Z) values have been determined at bumups of 150,6000.14000. and 20000 MWDIMTU.

Table 2.6.2 shows the Fca(z) penalty factors that are greater than 2ND per 31Effective Full Power Days. These values shaD be used to Increase the Fwa(z) asper Surveillance Requirement 3.2.1.2. A 2%/iS penalty factor shall be used at ancycle bumups that are outside the range of Table 2.6.2.

2.6.3 Uncertainty-

The uncertainty, UFO, to be applied to the Heat Fkux Hot Channel Factor Fa(Z)shall be calculated by the following formula

U, 0 = U.,, * .,

where:

Uq = Base FO measurement uncertainty = 1.05 when PDMS is inoperable.(Uq is defined by PDMS when operable.)

U. = Engineering uncertainty factor = 1.03

2.6.4 PDMS Alarms:

FC(Z) Warning Setpoint > 2% of Fo(Z) MarginFC(Z) Alarm Setpoint > 0% of FO(Z) Margin

CAC-02-48, Rev. 5 Page 7 of 17

CORE OPERATING LIMITS REPORT (couR) for BRAIDWOOD UNIT 2 CYCLE 10

-~~~~~~~~~~~~

Figure 2.6.1K(Z) - Normalized Fa(Z) as a Function of Core Height

0

0Z

0 1 2 3 4 5 6 7 8 9 10 11 12

BOTTOM Core Height (ft) ,TOP

CAC-0248, Rev. 5 Page 8 of J7

CORE OPERATING LIMITS REPORT (COlR) for BRAIDWOOD UNIT 2 CYCLE I 0

HeightFeet0.0D0.20Q400.60C8o1.CO1.201.401.601.802002.202.402.602z0ao.3.2031416O380400a.2044D4.604.80500&2D640a605.86.CO6.206.4D6.606.807.OD7207.407.607AO8.00B.208S.8608.809.0D9.209AO9.609.8010.0010.2010.4O10.6010.8011.0011.20IAdO

11.60MSD

1ZO

MAXWa)

1.0000

1.0000

3.00WD

1.00WlOW8.18821.18S2

1.16843.35891.14891.13993.13043.1228

1.1333

1340t1.14451.14721.34791.14861.14731.14501.14371.14331.15481.16561.18031.19201.20371.21251.2203122611.23381.2361.24361.24751.24631.247S1.24731.24191.2536

1.25451.25311.2484124701.2530IJOW8.00001.0000

1.0000

3.00001.0000

1.0000

1 eoo

Stoidwood Unl 2 Cycle 10

Flgur 26.62

SumTmwy ot W(a) Fundon at lSO MWK/VMU(rop ond 1ot*om IS% fxcbded pet WCAP- 10216)

1.35

1.30

1.25

1.15

1.10

V I

is1.C

0.0D 2.00 4.00 6.00 8.00 t0.00 12.00

CORE HEIGHT (FEET)

CAC-02-48, Rev. 5Page90of ]7

CORE OPERATING LTMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE J 0

HdV W3 War)F ee. Bldd.cUrfl 2 Cyde 100.00 3.00000.20 1.0000 Flfe2A2.b040 5.00000.60 I.00o0 Suvnray dW() Furacncgi60D MADMI U0.8o 3.00o0 CcprdBdtclm 15% Exedubdcjer WCP-0 3216)1.00 3.0o01.20 1.00D1.40 I.0l10 l.000 1.35

1.80 1.2t82 ._2.eo 1IS642.20 1.236n t _ _2.40 1.21_32.60 1.20792.80 MM96

-&OD L)"?R ~w10.00 ).ecoo

3.20 1.791 1.30

3ADo :.-3oo6nD 40 60 .0 OOO 10

11.40 1.1OR6HIGT FET

3.60 -,GM,eo O1O1547

.ZOD 1-34704.20 1-:3334.40 I' 303

4.80 3.127 12

5.8 1.0O3 06.00 3.0313

640 .3.1131m6.60 123326.80 1.33547.00 I' 4577.20 3.3541

7.60 3.I.6I 47.60 3.17671

8.20 335SAO0 1.37598.60 L3.378.80 3.17969.00 1.13309.20 1.37p5 1.309.40 3.179M9.60 3.19499.80 1.2030 F

10.0 J.209710.20 32135-------

10.60 1l000

31.00 1.000 o.oo 2.00 4.00 s.oo a.oo 10.Oo 12.0011.20 3.000011.40 1.000 CORE HEIGHT (FEET)11.60 3.0A0

12.0 3.0000

CAC-0248, Rev: 5Page 10 of 17


H1p M Wa)Feet0.00 1.0000D.20 I.oo000.40 L.0ooO0.60 1.0000.80 1.0000L.OD 000o7.20 1.00001.40 .000W1.60 1.000DL.80 1.37662.00 135727.20 1.33212.40 1.310tZ60 3.293 Iz28 3.2763.00 1.26323.20 1.24673.40 1.23183b60 1.21403.0 13.20434.0D 1.19474.20 3.18344.4D 1.17214hD 1.16094.80 1.14775.00 3.13415.20 1.13145.40 3.12375.6b 1.325s58 1.122.6.OO 1.12366.20 1.13246.4) 1.13826.60 1.14276.80 1.14497M 1.14647.20 1.14767.40 3.14647.60 1.1396

r7.8D * -1.357.8.OO 1.1306&20 1.12078.40 1.3 1318.60 1.10738.80 1.10349.0D 3.10509.20 1.10179.40 1.11339.60 1.11399.80 3.12S5tOO 1.15933020 1.389010.40 3.000010.60 1.00030.80 3.0000l1.00 I.00001120 1.000011.40 1.00011.60 1.000D11.80 1.0o012.OD 1.000D

Blddt7Urd32Cyde 10

Fi9e2.2.c

Sutrray et W(Z)Fuic~m d 14000 MvNOP U(rcpid Beffcn 15% ExduXedw WCAP-10216)

I

I..1 .1 _.1I

A -I

t I1 I I.i I

I.I f 41

13I I I. I I I I i-I I I I: It 1 I

CAC-02-4S, Rev. 5Page II of 17

CORE OPERATING LlMlTS REPORT (CoLR) for BRAIDWOOD UNIT 2 CYCLE Io

HvtFeela0.0Q200.400.600.801.00120VAD

1.602JO2.202AD2.602.a03.003.203A03.60

.004204A0

4805.00

5430

360D5.80

6.206Ao&.60

SSODam

7.207407.07.808.00

8.408.60

8.809.CO9.2D9.409.60980

10.0010.2010.010.60108o11.O011.201U.4011.6011.8012.00

mkxw~z)

130000

1.80001.8000D

L.00001.80000I.8000

I.C00D1.CODD

1.25t3

1.7317

1.2124

1.19661.1SS3

1.170D

1.161

1.16701.1657

1.7321.18421.1914

1.1969

12

1.2004

1.21651.22S01.23741241712433

1243?1.23S7

1 2326122216

1 61,.19551.1732

t.16331.14751.14351.1410

1.1833IJ1349

1.11511.2267

1640

1.3048I.0000

.00001.0000l.OOOD

1.000M

I.OCODl.0000

I.OOOD

1.0000

Brdd..dUrit 2 Cyde 0

Figpxe26.2.d

Surrroy diW(Z)Ftrdlmn d 2000 &ROMrU1cpid~cila Sn1% ExduxbpsWCAP-1 0216)

I

I I

t I I.I I

I I1 I

f I _I1 I

.1� -1

I.I I I i I

I I L L I I1. 1.

CAC-02-48, Rev. 5 Page 12 of 17

CORE OPERATING LIMITS REPORT (CoLR) for BRAIDWOOD UNIT 2 CYCLE 10

Table 2.6.2

Penalty Factors in Excess of 2% per 31 EFPD

Cycle Bumup Penally Factor - Fco(z)(MWD/MTlU) %)

2038 2.003068 3.133239 3.243411 3.30___3583 3.283754 3.183926 3_004612 _ 2.0410791 2.0010963 2.08

11477 2.32116-49 2.3811821 2.4111992 2.4612164 2.4742336 2-4512507 -- - 2.4112679 2.2712850 : 2.00

Notes- .

LUnear Interpolation is adequate for intermediate cycle bumups.

All cycle burnups outsidd the range of the table shall use a 2% penalty factor for compliance withthe 3.2.1.2 Surveillance Requirements.

CAC.02.48, Rev. S Page 13 of 17


2.7 Nuclear Enthaloy Rise Hot Channel Factor (F!M) (LCO 3.2.2)

2.7.1 FN. S F^,1.O + PFH(1 .0 - P)j

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER- ~~~Fr,"HP 1.70

PF = 0.3

2.7.2 Uncertainty when PDMS is inoperable

The uncertainty, UFaH, to be applied to the Nuclear Enthalpy Rise Hot ChannelFactor Fm shall be calculated by the following formula:

UFdH = UF',.m

where:

U&*,,= Base F'H measurement uncertainty =1.04

2.7.3 PDMS Alarms:

FKH Warning Selpoint 2 2% o F" 6 MarginF:, Alarm Setpoint 2 0% of FON Margin

2.8 Axial Flux Dilference (AFDI (LCO 3.2.3)

2.8.1 When PDMS Is Inoperable, the AXIAL FLUX DIFFERENCE (AFD) AcceptableOperation Limits are provided In Figure 2.8.1 or the latest valid PDMSSurveillance Report, whichever Is more conservative.

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

2.9 Departure from Nucleate Boiling Ratio :DNBR) (LCO 3.2.5)

2.9.1 DNBRAmPS 21.536

The Axial Power Shape Limiting DNBR fDNBRpW is applicable with THERMAL POWER2 50% RTP when PDUS is OPERABLE.

2.9.2 PDMS Alarms:

DNBR Warning Setpoint 2Ž2% of DNBR MarginDNBR Alarm Selpoint 2 Ž0% of DNBR Margin

CAC-o2-48 , Rev. 5 Page 14of17

CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE 10

Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power

CAC-02-4 8, Rev. 5 a 1Page 15 of 17


2.10 Reactor rno System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT SetpointParameter Values

2.10.1 The Overtemperature AT reactor trip setpoint K, shall be equal to 1.325-

2.10.2 The Overtemperature AT reactor trip seipoint Tw coefficient K2 shall be equalto 0.0297/ /F.

2.10.3 The Overiemperature AT reactor trip setpoint pressure coefficient K3 shall beequal to 0.00181 /psi.

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) Pi shall be equal to 2235 psig.

2.10.6 The measured reactor vessel AT lead~ag time constant r, shall be equal to8 sec.

2.10.7 The measured reactor vessel AT lead/lag time constant r2 shall be equal to3 sec.

2.10.8 The measured reactor vessel AT lag time constant r3shal be less than or equalto 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant r4shall be equal to 33 sec.

~2.10.10 The measured reactor vessel average temperature leadtlag tirme constant T.shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant Ts shall beless than or equal to 2 sec.

2.10.12 The f1 (Al) 'positive breakpoint shag be +10/ Al.

2.10.13 The 1s (A1) 'negative' breakpoint shall be -18% Al.

2.10.14 The f1 (Al) positives slope shall be +3.47% 1 % Al.

2.10.15 The f (Al) 'negative slope shag be -2.61%I % Al.

CAC-02-4 S, Rev. 5

_.CAC-)2-48, Rev. 5 Pg 6f1Page 16 of 17

CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE I0

2.11 Reactor TriP Svstem fATS) 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 setpoint T>, rate/lag coefficient Ks shall be equal

to 0.021 °F for increasing T,

2.11.3 The OverpowerAT reactor trip setpoint T., ratellag coefficient Ks shall be equal

to 01 OF for decreasing T..

2.11.4 The Overpower AT reactor trip setpoint T,, heatup coefficient K6 shall be equal

to 0.002451 'F when T > T.

2.11.5 The Overpower AT reactor trip setpoint T9heatup coefficient K6 shall be equal

toO IF when T:5 T.

2.11.6 The nominal T.> 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 t, shall be equal to

8 see.

2.11.8 The measured reactor vessel AT leadlag tire constant x2 shall be equal to

3 sec.

2.11.9 The measured reactor vessel AT lag time constant vr shall be less than or equal

to 2 sec.

2.11.10 The measured reactor vessel average temperaturelag time constant 'sshall fU

less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant s7

shall be equal to 10 sec.

2.11.12 The 12 (A) 'posftive' 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 12 (A) 'positivf' slope shall be 0 for all Al.

2.11.15 The 2(Al) 'negative slope shall be 0 for all Al.

CAC-02-48 Rev. 5 Page 17 of 17


2.12 Reactor Coolant System (RCS) Pressure. Temperature, and Flow Departure fromNucleate Boilina (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..) 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 1733 ppm(LCO 3.9.1).

2.13.2 To maintain keff < 0.987 with all shutdown and control rods fully withdrawn inMODES 3.4, or 5 (TRM 31 .g Required Action B.2 and TRM TLCO 3.1 .k.2), theReactor Coolant System boron concentration shall be greater than or equal to:

a. 1778 ppm prior to initial criticalityb. 1990 ppm at all other times In core life.

Braidwood Station, Units 1 and 2, Core Operating Limits ... · Attachment 2: Core Operating Limits Report for Braidwood Unit 2 Cycle 10 (CAC-02-48, Revision 5) cc: Regional Administrator

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