Byron Station, Unit 2, Issuance of Core Operating Limits ... · Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455 Subject: Issuance of Core Operating

FV

Exelkns.Exelon Generation Company, LLCByron Station4450 North German Church RoadByron, IL 61010-9794

www.exeloncorp.com Nuclear

April 5, 2004

LTR: BYRON 2004-0036File: 2.01.0700

United States Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555-0001

Byron Station, Unit 2Facility Operating License No. NPF-66NRC Docket No. STN 50-455

Subject: Issuance of Core Operating Limits Report for Byron Station Unit Two Cycle 12

Reference: Licensee Event Report 454-2003-003-01, 'Licensed Maximum Power LevelExceeded Due to Inaccuracies in Feedwater Ultrasonic Flow Measurements," DatedMarch 31, 2004

In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we aresubmitting the COLR for Byron Station, Unit 2 Cycle 12.

The cycle 12 core contains 85 new fuel assemblies, 88 once burned assemblies and 20 twiceburned assemblies. All the new assemblies contain Integral Fuel Burnable Absorbers and all 8 ofthe twice-burned assemblies have had their top nozzle replaced due to the potential top nozzlescrew fracture problem.

The nuclear design and safety analyses also considered the possible effects from overpoweroperation of Byron Station Unit 2 that may have occurred due to the inaccuracies in the UltrasonicFlow Measurement System flow correction factors. (See reference 1)

Should you have any questions concerning these reports, please contact William Grundmann,Regulatory Assurance Manager, at (815) 406-2800.

Respectfully,

Stephen E. KuczynskiSite Vice PresidentByron Nuclear Generating Station ,\ oo |

Attachment: Byron Station, Unit 2 Cycle 12, COLR

cc: Regional Administrator - NRC Region IIINRC Senior Resident Inspector - Byron StationNRC Project Manager - NRR - Byron StationIllinois Emergency Management Agency - Division of Nuclear Safety

Attachment

Byron Station, Unit 2 Cycle 12, COLR

CORE OPERATING LIMITS REPORT (COLR)

FOR

BYRON UNIT 2 CYCLE 12

Page I of 16

CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12

1.0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 12 has been prepared inaccordance 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 (FNm)

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 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 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)

Page 2 of 16


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. Theselimits have been developed using the NRC-approved methodologies specified In Technical Specification5.6.5.

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

2.1.1 In MODES 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS)highest loop average temperature, and pressurizer pressure shall not exceed the limitsspecified in Figure 2.1.1.

6 80

680- .-

2471 psia

660

2250 psia

64 0

I-- 620 __ _ _

a)On

600

.c8D

Froction of Nominol Power

Figure 2.1.1: Reactor Core Limits

Page 3 of 16


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 SDM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs3.1.1 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 BOLUARO/HZP-MTC upper limit shall be +2.17 x 105 Ak/kPF.

2.3.2 The EOLJARO/HFP-MTC lower limit shall be -4.6 x 10' 4k/k/0F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/OF.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 Ak/k/0F.

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 (LCO 3.1.6)

2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited Inphysical 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 orequal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, BankC 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 followingoverlap limits as a function of park position:

Park Position (step) I Overlap Limit (step)228 113

Page 4 of 16


Figure 2.5.1:Control Bank Insertion ULmits Versus Percent Rated Therml Power

(2704 224) (7704 224)

.-...-..... ,-1,,----1)..

e .-; (100%, 161)C3 160oc

*140

QC.e 120C0-100U)0a.C 80mso

0 60

40

20

0

0 10 20 30 40 50 60 70

Relative Power (Percent)

80 90 100

Page 5 of 16


2.6 Heat Flux Hot Channel Factor (F("Z (LCO 3.2.1)

2.6.1 Total Peaking Factor:

QRTP

FQ (Z) < -xK(Z) for P S0.50.5

FRTP

FQ(Z) < FQ xK(Z) forP>0.5

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

Fo" = 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 150, 6000,14000, and 20000 MWDIMTU.

Table 2.6.2 shows the FCo(z) penalty factors that are greater than 2% per 31 EffectiveFull Power Days .(EFPD). These values shall be used to increase the Fwo(z) as perSurveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnupsthat 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 becalculated by the following formula

U0=U,. , *Ug

where:

Uw = Base F0 measurement uncertainty = 1.05 when PDMS is inoperable(Uqu is defined by PDMS when OPERABLE.)

U. = Engineering uncertainty factor = 1.03

2.6.4 PDMS Alarms:

Fo(Z) Warning Setpoint Ž 2% of Fo(Z) MarginFO(Z) Alarm Setpoint 2 0% of Fo(Z) Margin

Page 6 of 16


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

(0.0 1.0) (6.0,10)

10--1 1 1 1 1 1ll l { I0.9_ _ - -…

0.8 --

~0.7- -

ILe

0.6U 0.6 - _

E~ 0.5 -- … = =

- - - - - }_-4-LOCA Limiting0y.4_ PEfnvlinas I

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

Page7of 16


H4ogtFeem0.000.200.400.600.801.001.201.401.601.802.002.202.402.602.803.003.203.403.603.804.004204.404.604.805.005.205.405.605.806.006.206.406.606.807.007.207.407.607.808.008.208.408.608.809.009.209.409.609.8010.0010.2010.4010.6010.8011.0011.2011.4011.6011.8012.00

MAX W(Z)

1.00001.00001.00001.00001.00001.00001.00003.00001.00001.23371.20871.19411.18631.17591.16941.16761.16431.16211.15751.15321.1482I.14161.13521.13121.12171.12461.12111.12061.12411.1271.14041.15221.16401.17191.17981.18581.18911.19021.19041.1 962100412031120661.21231.21401.2122121811.22751.23551.24371.25101.25421.00001.00001.00003.00001.00001.00001.00001.00001.0000

Byn Urit 2 Cyde 12

rlgie 2.6.2.a

SumrneydW(Z)Fmon at 150 ANDh U(T cpad8cm9ex E15% Exdup WCAP-10216)

1.35

1.30

1.25

z0

Z 1.20

1.15

1.10

I I -I

-

4

-I.4.4

4.

4- -_ - - -4.

- - -4-- -

4--

4 4- - - 4 -

4

* 44.

-

-

- . -

-- - - -

-

…- - -I flg0.00 2.00 4.00 6.00 8.00

CORE HEIGHT (FEET)

10.00 12.00

Page 8 of 16

CORE OPERATING UMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12

0Q000.200400.600.801.001.201.401.601802002.202.402.602.803.003.203.403.603.804.004.204.404.604.805.005.205.405.605.806.006.206.406.60680 -7.007.207.407.607.808.008.208:408.608.809.009.209.409.609.80

10.lO10.2010.4010.6010.6011.0011.2011.4011.6011.8012.00

Max W(Z)

1.00001.00001.00001.00001.00001000010000

l.OOOI1.0001.2300121021.19201.17891.16941.16s21.1602I.15331.14641.13841.13051.12251.11261.10942.20521.2022l.09851.093Bl.0900I.08502.0925I.l0021.1069'1.1 1761.13281.14941.16421.17801.19031.2014121111.21971.226712.191.2352I.3862.24622.2616

1.27631.289223029

13148132441.00001.00001.00001.00001.00001.00001.00001.00001.0000

Byron Urit2 Cyde 12

Figire2.6.2.b

.SLTrryd W(2) Funbcn a 600D O NDM U(T cp a-d Bctcon 15% Exdb1d pE WCAP.10216)

Page 9 of 16


Hd6gtF eet0.000.200.400.600.801.001.201.401.601.802.002.202.402.602.803.003.203.403.603.804.004.204.404.60J.805.005.205.405.60.5.806.006.206.406.606.807.007.207.407.607.808.008.208.408.608.809.009.209.409.609.80

10.0010.201.4010.6010.8011.0011.2011.4011.6011.8012.00

MAX W(2)

1.0000

1.00001.0000I.00001.00001.00001.00001.0000I2692I125202349

I.2I92I 20291.19321.1391.174SI.I6561.16011.156S1.1535I.I4871.24311.13631.13171.13431.1359I.I3741.14I21.15661.1710I.I8t72.I914I.I9831203II.2059l1049120291.19601.I8911.1793I.I6651.15962.15 28l.15122.15432.25532.25782.1591l.l880I2190I.24701.00001.00001.00001.00001.00001.00001.00001.00001.0000

Byal U rit 2 Cyde 12

Flgxe 2.62.c

Sunrry d WtZ) FLrdcn mS 14000 MNDMr U(lcpsalBcatcnl5% ExdudedapWCAP.10216)

1.35

1.30

1.25

a0

P120

1.15

1.10

1.05

0.

..-.-. -- --. ..-. …

I . . - .-

�…

4 ____

4 - ..

4

4

4 .4 4-__- -.

*4

t I ________

100 2.00 4.00 6.00 8.00

CORE HEIGHT (FEET)

10.00 t2.00

Page lOof 16


HeipFeM0.000200.400.60.0.801.0o1.201.401.601.802.002.202.402.602601001203.403.603.804.004.204.404.604.80s.m5.205.405.605.806.006.206.406.606.807.007.207.407.607.80B.008.208.408.608809.009.209.409.609.80

10.0010.2010.4010.6010.8011 .011.2011.4011.6011.8012.00

MAX W(Z)

1.0000L.O001.00001.0000

o0000l.0000l.OXODl.OOCOl OXO1126281.24491.22871.21891.20611.1943I.I8 161.17341.17891.1832I.13681.l8881.18901,18741.1949120231.20751.2115121491227512J38

2572126781.27551.27t212t8001277812708126281248812359121911.19841.1777l1.5321.15131.15101.15411.16001.204012430127701.30901.00001.00001.00001.00001.00001.00001.00001.00001.0D00

Brw Unt 2 Cyde 12

F giue 2.6.2.d

S txnrTry d WJZ) Ftxrlon at 20000 MNDAlT U( np Edx BrSn 15% Exdu dpe WCAP-10216) -

1Ao

1.35

1.30

z *.Cu

0F

E'a-

1.20

1.15

* 1.10

u..v.z _

____ 4

- - - - V - - - - - -

* -- I.. -.

� . 44---4

..-- .4 4

-1�

1.050.00 2.00 4.00 6.00 8.00 10.00

CORE HEIGHT (FEET)

12.00

Page I I of 16


Table 2.6.2

Penalty Factors in Excess of 2% per 31 EFPD

Cycle Burnup Penalty Factor - FcQ(z)(MWD/MTU) (%)

150 2.13. 322 2.50

494 2.44*666 2.33

838 2.141010 2.00

4624 2.004796 2.084968 2.305141 2.365313 2.285485 2.105657 2.00

Notes:

Linear Interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of the table shall use a 2% penalty factor for compliance with the3.2.1.2 Surveillance Requirements.

Page 12 of l6


2.7 Nuclear Enthaloy Rise Hot Channel Factor (FN) (LCO 3.2.2)

2.7.1 FOM < FrrP[l.0 + PFwi(1.0 - P).

where: P = the ratio of THERMAL POWER to RATED THERMAL POWERF = 1.70PFAH= 0.3

2.7.2 Uncertainty when PDMS is inoperable

The uncertainty. UFH, to be applied to the Nuclear Enthalpy Rise Hot Channel FactorFNH shall be calculated by the following formula:

UF6H = UFMHm

where:

Uss,,, = Base F%.1 measurement uncertainty = 1.04

2.7.3 PDMS Alarms:

0N&j Warning Setpoint 2 2% of F",i MarginF| .H Alarm Setpoint 2 0% of FN" Margin

2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3)

2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable OperationLimits are provided In Figure 2.8.1 or the latest valid PDMS 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 (DNBRApsI) is applicable with THERMAL POWER2 50% RTP when PDMS Is OPERABLE.

2.9.2 PDMS Alarms:

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

Pape 13 of 16


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

*1*

Axial Flux Difference Limits.with

PDMS Inoperable

120

100

-3

cca:

I-0LuJ

cc*4-.0

p-

80

60

40

(-15, 10 ) +10,100)

Unac eptable Un cceplableOp ration .. . 0 eratimn

A cceptableC perat on

5, 50) .(+25, ) . -

, , I

20

0-50 -40 -30 -20 -10 0 10 20 30 40 50

AXIAL FLUX DIFFERENCE (%)

Page 14 of 16


2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT SetpointParameter 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 T.,, coefficient K2 shall be equal to0.0297/ "F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to0.00181 /psi.

2.10.4 The nominal Tavat 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 2235 psig.

2.10.6 The measured reactor vessel AT lead/lag time constant 't1 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 t3 shall be less than or equal to 2sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant 14 shall beequal to 33 sec.

2.10.10 The measured reactor vessel average temperature leadAag time constant '15 shall beequal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant X6 shall be lessthan or equal to 2 sec.

2.10.12 The f (Al) 'positive' breakpoint shall be +10% Al.

2.10.13 The fl (Al) 'negative' breakpoint shall be -18% Al.

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

2.10.15 The fI (Al) "negative' slope shall be -2.61 /% Al.

Page 15of 16


2.11 Reactor Trip Syslem (RTS) Instrumentation (LCO 3.3.1) - OverpowerAT Seipoint ParameterValues

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 Tavg rate/lag coefficient Ks shall be equal to0.02 / 0F for increasing TM.

2.11.3 The Overpower AT reactor trip setpoint Tav, rate/lag coefficient K5 shall be equal to0 / 0F for decreasing Tan.

2.11.4 The Overpower AT reactor trip setpoint T.vg heatup coefficient K6 shall be equal to0.00245 /'F when T > T.

2.11.5 The Overpower AT reactor trip setpolnt Tvg heatup coefficient K(6 shall be equal to0 /'FwhenTsT".

2.11.6 The nominal T,9 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 a, shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT leadAag time constant 12 shall be equal to 3 sec.

2.11.9 The measured reactor vessel AT lag time constant X3 shall be less than or equal to 2sec.

2.11.10 The measured reactor vessel average temperature lag time constant x6 shall be lessthan or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant r7 shall beequal to 10 sec.

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

2.11.13 The 12 (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.

Page 16of 16


2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from NucleateBoiling (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 OF.

2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.

2.13 Boron Concentration

2.13.1 The refueling boron concentration shall be greater than or equal to 1781 ppm (LCO3.9.1).

2.13.2 To maintain keff S 0.987 with all shutdown and control rods fully withdrawn in MODES 3,4, or 5 (TRM TLCO 3.1.9 Required Action B.2 and TRM TLCO 3.1.k.2), the ReactorCoolant System boron concentration shall be greater than or equal to:

a. 1864 ppm prior to Initial criticality.b. 2048 ppm at all other times in core life.

Documents

Byron Station, Unit 2, Issuance of Core Operating Limits ... · Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455 Subject: Issuance of Core Operating