BYRON 2014-0002, Cycle 19 and Unit 2 Cycle 18 Core Operating Limits Report for Measurement Uncertainty Recapture (Mur) Power Uprate

Cycle 19 and Unit 2 Cycle 18 Core Operating Limits Report for Measurement Uncertainty Recapture (Mur) Power Uprate

ML14044A017
Person / Time
Site:	Byron
Issue date:	02/13/2014
From:	Kearney F Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
1.10.0101, 2.01.0300, BYRON 2014-0002
Download: ML14044A017 (33)

Text

Byron Generating Station 4450 North German Church Road E xe[on Generat i on February 13 2014 LTR: BYRON 201 4-0002 File: 2.01 .0300 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos, NPF-37 and NPF-66 NRC Docket No, STN 50-454 and 50-455

Subject:

Byron Station Unit 1 Cycle 19 and Unit 2 Cycle 18 Core Operating Limits Report for Measurement Uncertainty Recapture (MUR) Power Uprate

References:

Letter from Craig Lambert (Exelon Generation Company, LLC) to U. S. NRC, Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate, dated June 23, 2011 In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR), we are submitting updated versions of the Unit 1 COLR for Cycle 19 and the Unit 2 COLF for Cycle 18. The COLRs are updated to address Pressure and Temperature impacts due to the Measurement Uncertainty Recapture (MUR) Power Uprate Licerse Amendment Request for Byron Units 1 and 2 submitted under letter RS-1 1-099, dated June 23, 2011.

Should you have any questions concerning this report, please contact Steven Gackstetter, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully, therA.

Site Vice President Byron Statioi FAK/G C!sg Attachments 1. Byron Station Unit 1 Cycle 19 COLR

2. Byron Station Unit 2 Cycle 18 COLR cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT I CYCLE 19 EXELON TRACKING ID:

COLR BYRON I REVISION 9

COLR BYRON 1 Revision 9 Page 1 oflS CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit I Cycle 19 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 (FQ(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH)

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 I and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) MODE 5 TRM TLCO 3.1.] Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)

COLR BYRON 1 Revision 9 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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) 2.1.1 In MODES I 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.

ci) ci) ci)

E ci) ci.)

(3 ci) 0 0.2 0.4 0.6 0.8 1 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 1 Revision 9 Page 3 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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.]).

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 TLCOs 3.1.i and 3.1.]).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +1.481 x 10 Ak/k/°F.

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

2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i0 4 AkIkI°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10 AkJk/°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 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 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) 231 115

COLR BYRON 1 Revision 9 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (26.52%, 224) (76.96%, 224) 220 200 180 160 (100%, 161) 140 U,

120 0

U, 100 0

60 40 20 0

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

COLR BYRON 1 Revision 9 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 2.6 Heat Flux Hot Channel Factor (F (LCO 3.2.1) 2.6.1 Total Peaking Factor:

P T

FR FQ (Z) xK(Z) for P 0.5 FRTP FQ (Z) xK(Z) for P > 0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTF= 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z) Normalized FQ(Z) as a Function of Core Height 1.1

[1222]

(12.0,0.924)1 0.9 0.8 RI 0.7 a

LI..

0.6 LOCA Limiting 0.4 Envelope 0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 1011 12 BOUOM Core Height (ft) TOP

COLR BYRON 1 Revision 9 Page 6 of 15 CORE OPERAflNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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 as:

1) Table 2.6.2.a are the normal operation W(Z) values for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.

2) The EOL-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups 18000 MWD/MTU. The EOL-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1 .b. The EOL-only normal operation W(Z) values have been determined at bumups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOL-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.

Table 2.6.2.c shows the FCQ(Z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the F (z) as per 0

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.c.

2.6.3 Uncertainty

The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula UFQ = Uq

• U where:

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

0 U = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

(Z) Warning Setpoint = 2% FQ(Z) Margin 0

F F

(

0 Z) Alarm Setpoint = 0% FQ(Z) Margin

z D F I I- 0) C- C- U) U) 10 C) 0 CD 0)0) 0 CD F- (4 3) U) F-. (1 C) CO CC) (4 (4 0) F CO 0) 0 (4 (1 L) C)

C4 F-. C C- C) C) CD 0 1) U) F-- F-. U) CD 0) U) F-. 3) 0 CD CD C) (4 F- 0) 0) U) U) C) C) CD 3) 0)

In 0 0) CD U) C) CJ 00) CD F-. CD CO CD CO 0 F-. F F- C- CD U) C) -O) CD F- C F- F- CD 0 CD C) U) F- U)

-4 a (C (4 (4 CC (4 -

4-4 L) CD Ci 0

a) 0)

C U C

D E 0) CD 0 C) 0 CC CO 0) C) CD C) CD (4 0 0 CD Ci U) 0) C) 0 CD 00 U) CC) U) U) U) F- U) C) CD 0) 00) 0) 0 F- CN F- CD C) 0 CD U) C) 0 F- 0) U) U) C C CD CD C) 0 C4 CD (I U) (4 CD CO CO CO 0 C) CD F CD -0 C) CO CO U) F- U) 0 U) CO CD F- C) 0).- (4 U) CO F- F- CD 0) U) C) 0) 0 F- 00 F- 0 F- 0 .0 OCDF- F- C)C10 0)F- CO C) 0 0) 0)CDC-CDU) U) C)C)C) C)C)C) C)U)F- CD 0)0 00 0)CDF- F- CC-- -CD CD 0)OC4 C) (4 CCOCD C

OFC a)

Ca 0)

Co 0,

C

.0 C

c-)

i Co F- CD C4 0) 0) F- U) (1 0) CD CD C)4 F-. C) 0 F- (4 C)4 F- CD F- CD CO 0) F-. (C F- F- CO (4 0) ,- C) C4 F-. CD 0) CO F- F- 0) (4 0) (4 0)

C, <.

.D o1 U.

0) 0 0 I 0).- 0) C) CD C) 0 CD CO (4 CD U) U) CD U) (4 CD (1 CD IN CO CO CO F- CN 0 (0 CD 00 C C) (4 0)

C) IN CD 00 U) CO 0 0) CD C) 0) CD U) (C CD 0 U) a U) C) CO CD CO F- 00) U) F-. CD 0) U) C) 0 F- 00 F- C) F- 0) 00 0) 0 CD 0 4 C) U) F- CO CD U) CD 0 F-. CD C) 0 1.4 0

0 C 0

CC U. 000 0 00000000000000000000000000000000000000000 00 0 0)0 CCO OC4 0

. V2 deo U)U)U)U)U)C0CDCOCDCDFF-CDCDCDCD0)0)0)0) 0 I 0 q 0 00 (4 0 ZCN

0 C

CC 0 ID 0 0 0 0

0 -z

.-Dppp 0 0 0 (0 0) 44 0000 8

0) (3 0 01 0) . P.) 0 0 01 0) P.) M0010010).(00010)01b010)P..P.) CD CD I 000000000 0 0 0 0 0 0000000000000000000000000000000000 0

-1 C 8: 0 0_

3 CD 0 rn 0.00 g c 3

j CD 01 0) (0 0 0 01 0) Ca 00) P.) 0 4 4 4 .1 0) CD P.) C.) 01010101 C.) P.) CD 0) 01 01 4 .4 0)0)01 Ca P.) P.) 1<3 (<3 P.) C.) CI) 0)0) 4 CO 01 0 - (<3 0) 0 3 ..<

C.) CD CII (<3 - Ca 01 C.) (3) 3 01 0 0) 0) 01 C.) C.) 0) - C.) - 01 0 . - 01 .4 0) C.) (31 - C.) - CD . -4 000 . CD 01 01 4 C.) 0 01 C)) - 01 - 0) 0) 01 0) C.) 0 0)010)0101 (31 P.) 1310 C.) 0 C.) 01 0) COlD CO 4 0) -I - 01 -(1. 4 C.) 0) C.) P.) (3 0 (3100)10 C.) <31 01 0) 0)10 4 0) ..4 CD P.) 01 0 .1 4 - (<3 . 0) 0 C.) ... 0 0. -

C 03 m-ag 0 DC 0.,

I go.ID . . C.) Ca Ca IS) P.--- P.) P.) P.31<3 P.) 1.) P.) P.) P.) (3 P.) P.) P.) P.) P.) (3 P.) P.) P.) 0 0 P.) - - C.) CD - . .

(001 C.) - Ca CI) CII (0(0 -4 II. P.) C.) 01 0) 0 CD 4 01(0 01 01010 4 - - 4 P.) 0) -4 1 CII Ca 00) (.3(0 -4 0) J C)) Ca 0 4 (310 010) C.) COO 0 > -nC.

00)0) .4 IS) 1.3 0 CD Ca 0) .4 CD P.) . I-.) 0101 Ca 1.) .4 01 . COP.) -1 0) 0(010(0 Ca 0) - Ca .4 0) 01 . Ca 0) . 00) Ca 4 0001 .4 010 P.) CD CI) -4 P.).4 0 0 C

0 P.)

C.) P.) PS) P.) (3M )P.)

0- P.) 01 -4 CII 0) 0)..,..P.3IS3---.l.PS)C.).0ICI10) -4 P.) 01 C.) COlD -4 CD -4 01 C.) 00) (.3 CD 40) -1CI) C.) 0 -4(11 0 COO 0(1)0) -4 0) .11.1.3 01 CO P.) -.4 0) - . 00) . Ca - - -4000) .4(31 0 P.) 40 CD - :-

-4 C o0 I 0 z

COLR BYRON 1 Revision 9 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWDIMTU) FCp(z) 0 1.0416 150 1.0416 326 1.0464 502 1.0499 677 1.0520 853 1.0518 1029 1.0506 1380 1.0437 1908 1.0246 2083 1.0200 15969 1.0200 16320 1.0223 17199 1.0275 18078 1.0300 18605 1.0307 19836 1.0267 20011 1.0200 24301 1.0200 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 the 3.2.1.2 Surveillance Requirements.

COLR BYRON 1 Revision 9 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN (LCO 3.2.2) 2.7.1 FNAH F[1 .0 + PFH(1 .0 P)]

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

2.7.2 Uncertainty

The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNH shall be calculated by the following formula:

UFAH = UFAHm where:

UF4Hm = Base FH measurement uncertainty = I 04 when PDMS is inoperable (UFAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FH Warning Setpoint = 2% FH Margin FH Alarm Setpoint = 0% FH 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 the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.

b) Figure 2.8.1 .b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1 .b, confirm that the plant is within the specified AFD envelope.

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

2.9.2 PDMS Alarms:

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

COLR BYRON 1 Revision 9 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 Figure 2.8.1.a:

Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)

Axial Flux Difference Limits with PDMS Inoperable 120

(-15 100) i-I-b, 00) 100 w Unacc ptabl Una cepta le 0 80 Ope ation

) 0 eratio 0

-J / A cepta C perath fi LU 60 I

J Ui

(-3 , 50) (+ 5, 51 )

40 4-0 20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 1 Revision 9 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 Figure 2.8.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup 18000 MWDIMTU)

Axial Flux Difference Limits with PDMS Inoperable 120 100 uJ 0

a 80 Ui

= 60 I

Ui I

40 0

20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 1 Revision 9 Page 13 oflS CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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 K 1 shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/ °F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K 3 shall be equal to 0.00135 / psi.

2.10.4 The nominal Tavg 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 t 1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel AT lag time constant 3 t shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant t 4 be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant t shall be 5

equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 6 t 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% / % Al.

2.10.15 The f1 (Al) negative slope shall be -2.61% I % Al.

COLR BYRON 1 Revision 9 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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 K 4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K 5 shall be equal to 0.02 / F for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K 5 shall be equal to 0 / F for decreasing Tavg 2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K 6 shall be equal to 0.00245 / °F when T > T.

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K 6 shall be equal to 0/ F when T T.

2.11.6 The nominal Tavg 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 1 shall 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 t 3 shall be less than or equal to 2 sec.

2.11 .10 The measured reactor vessel average temperature lag time constant u 6 be less than or equal to 2 sec.

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

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

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

2.11.14 The f2 (Al) positive slope shall be 0 for all Al.

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

COLR BYRON 1 Revision 9 Page 15 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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 (Tavg) 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 the applicable value given in the Table below (LCO 3.9.1). The reported prior to initial criticality value also bounds the end-of-cycle requirements for the previous cycle.

2.13.2 To maintain keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or5 (TRM TLCO 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 the applicable values given in the Table below.

COLR Boron Concentration Conditions Section (ppm) 2.13.1 a) prior to initial criticality 1693 b) for cycle burnups 0 MWD/MTU 1788 and < 16000 MWD/MTU c) for Cycle Burnup 16,000 MWD/MTU 1439 2.13.2 a) prior to initial criticality 1772 b) all other times in life 1987

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 18 EXELON TRACKING ID:

COLR BYRON 2 REVISION 6

COLR BYRON 2 Revision 6 Page 1 oflS CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 18 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 (F(Z))

0 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH)

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 I and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) MODE 5 TRM TLCO 3.1 .j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)

COLR BYRON 2 Revision 6 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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) 2.1.1 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 limits specified in Figure 2.1.1.

U ci) ci) ci) cl E

ci) ci) 0 02 0.4 0.6 0.8 I2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 2 Revision 6 Page 3 ofl5 CORE OPERATThTG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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 TLCOs 3.1] and 3.1.j).

2.3 Moderator Temrerature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +1.839 x i0 Ak/kJ°F.

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

2.3.3 The EOIJARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i0 4 AkIkI°F.

2.3.4 The EOLJARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10 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 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 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) 231 115

COLR BYRON 2 Revision 6 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Figure Z5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (?62%, 224) (76.96%, 224) 220 7

200 71 BANK B 180 60 7 7 (100%, 161)

I°° 163)

ZK z

7/

4K01_

/ /

&60 40 g 7/

20 0

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

COLR BYRON 2 Revision 6 Page 5 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 2.6 Heat Flux Hot Channel Factor (FQ)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FRII FQ(Z) --xK(Z) forP0.5 FRII FQ(Z) 2 ----xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTF= 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z) Normalized FQ(Z) as a Function of Core Height 1.1 (0.0 1.0) (6.0 1.0) 121 0.924) 0.9 0.8 0.7 a

U 0.6 LOCA Limiting i Envelope 0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 1011 12 BOTIOM Core Height (ft) TOP

COLR BYRON 2 Revision 6 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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 as:

1) Table 2.6.2.a are the normal operation W(Z) values for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at bumups of 150, 6000, 14000, and 20000 MWD/MTU.

2) The EOL-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups 18000 MWD/MTU. The EOL-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1 .b. The EOL-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOL-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.

Table 2.6.2.c shows the FQ(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the F (z) as per 0

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.c.

2.6.3 Uncertainty

The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula UFQ = Uqu

• U where:

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

Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

FQ(Z) Warning Setpoint = 2% FQ(Z) Margin FQ(Z) Alarm Setpoint = 0% FQ(Z) Margin

0 Ow 0 b 1 0

C 03 C) 0 p 0 tIC b C CD 0 0 0 0 0

2.

Ic 0 C 3

T1

0) N (DO

<0 (DO C

Ct31) -

00

• oO C

C 0-I w

0D 0:

(D<

I

-no.

0 000 Co.

0 C 0

C 0 .----

n, -

C Q

A ii I C C

CD

-IC a C A

3z (1 0

0 0

-..1 0 C) PC 0 0 010) 01:-

0000 00000000 0 00 00 0 0

V 0

0 0

0 a 0 N C.) 0) .4 .40) Cs) CD 0) C.) 0010) 4 44 -1 COO Cs) C.) (Cl (21 (21 C,) 2.3 - 10014 10)0)01 2,) -a- I) N C.) C.) (Cl 010)02-102 COO ..O w r 1001 2.32)1 1001C0-4O 002 CO:--0)40)0Cs30 CD 101002(0 3 0 C 3 .<

o. -i 0

00 C.) . :-  :- C.) C.) C.) C,) Si F.) Is) 253 Is) CS) Is) 2.3 N Is) Is) Is) Is) Is) I.) Is) -----

C.)CII01401IDNC.)OO 00OO-(04010). 253001010101(0- -.1O:--4CD01Is)()1 (DC.) C.):- C.)4C.)O )NMC.)P301 IsiOl-C,)IOO)

C 0 Is) 2.)

0*

0

(

oo.

S)iS) F.333 01:- CO -4 401CO-c.):-01 N Fs)Is) C.)

0) 0) .--2s3 -4 C.) 01 CO 10 (21 10 2.3 0) 0 Is) -4 0 000 0 -4 Ql01:-NO0101 0 N N(S)

C 0 z

COLR BYRON 2 Revision 6 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCQ(z) 0 1.0200 852 1.0200 1028 1.0276 1203 1.0380 1379 1.0447 1554 1.0492 1730 1.0478 1905 1.0460 2081 1.0440 2256 1.0420 2432 .0394 2608 .0366 3661 .0200 16651 .0200 16826 1.0227 17353 1.0294 17879 1.0288 18582 .0276 19865 .0200 24302 .0200 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 the 3.2.1.2 Surveillance Requirements.

COLR BYRON 2 Revision 6 Page 10 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNj (LCO 3.2.2) 2.7.1 FH F[1.0 + PF(1.0 P)]-

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER tRTP AH 1

PFAH 0.3

2.7.2 Uncertainty

The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FH shall be calculated by the following formula:

UFH UFAHm where:

UFAHm = Base FH measurement uncertainty = 1.04 when PDMS is inoperable (UFm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FNAH Warning Seipoint = 2% FH Margin FH Alarm Setpoint = 0% FNAH 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 the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.

b) Figure 2.8.1 .b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1.b, confirm that the plant is within the specified AFD envelope.

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

2.9.2 PDMS Alarms:

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

COLR BYRON 2 Revision 6 Page 11 oflS CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Figure 2.8.1.a:

Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)

Axial Flux Difference Limits with PDMS Inoperable 120

(-15 100) +10, 00) 100 Ui Unac ptabl Una cepta le Ope ation 0 80 ) \ 0 eratioi I / A ;cepta C perati Ui 60 I

=

I

.J

• (-3 5, 50 (+ 5, 5 )

40 20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 2 Revision 6 Page 12 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Figure 28.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup 18000 MWD/MTU)

Axial Flux Difference Limits with PDMS Inoperable 120 100 Er LU 0

a- 80

-J LU

= 60 I

LU I

40 II..

0 20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 2 Revision 6 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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 K 1 shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.02971°F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K 3 shall be equal to 0.00135/ psi.

2.10.4 The nominal Tavg 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 t shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel AT lag time constant t shall be less than or equal to 2 3

sec.

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

2.10.10 The measured reactor vessel average temperature lead/lag time constant t 5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 6 t 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% / % Al.

2.10.15 The f1 (Al) negative slope shall be -2.61% / % Al.

COLR BYRON 2 Revision 6 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 2.11 Reactor TIID System (RTS) Instrumentation (LCO 3.3.1) Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint 1<4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K 5 shall be equal to 0.02 / °F for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient 1<5 shaN be equal to 0/ °F for decreasing Tavg.

2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K 6 shall be equal to 0.00245 / °F when T > T.

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient 1<6 shall be equal to 0 / °F when T T.

2.11.6 The nominal Tavg 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 1 shall be equal to 8 sec.

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

2.11.9 The measured reactor vessel AT lag time constant t 3 shall be less than or equal to 2 sec.

2.11 .10 The measured reactor vessel average temperature lag time constant 6 t shall be less than or equal to 2 sec.

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

COLR BYRON 2 Revision 6 Page 15 ofl5 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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 (Tavg) 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 the applicable value given in the Table below (LCO 3.9.1). The reported prior to initial criticality value also bounds the end-of-cycle requirements for the previous cycle.

2.13.2 To maintain keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or5 (TRM TLCO 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 the applicable value given in the Table below.

COLR Conditions Boron Concentration Section (ppm) 2.13.1 a) prior to initial criticality 1696 b) for cycle burnups 0 MWD/MTU 1778 and < 16000 MWD/MTU c) for cycle bumups 16000 1393 MWD/MTU 2.13.2 a) prior to initial criticality 1733 b) all other times in life 1953