BYRON 2003-0079, to Byron, Unit 1 Cycle 12, Core Operating Limits Report and Revision1 to Byron, Unit 2 Cycle 11, Core Operating Limits Report

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ML032521322
Person / Time
Site: Byron  Constellation icon.png
Issue date: 08/28/2003
From: Kuczynski S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.01.0700, BYRON 2003-0079
Download: ML032521322 (37)
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Text

Exe tnM Exelon Generation www.exeloncorp.com Nuclear Byron Generating Station 4450 North German Church Road Byron, IL 61010 -9794 Tel 815-234-5441 August 28, 2003 LTR: BYRON 2003-0079 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Units I and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

Revision 3 to Byron Station, Unit I Cycle 12, Core Operating Limits Report and Revision 1 to Byron Station, Unit 2 Cycle 11, Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the revised COLRs for Byron Station, Unit 1 Cycle 12, and Byron Station, Unit 2 Cycle

11. This revision of the Unit I and Unit 2 COLRs changes the minimum Reactor Coolant System total flow rate from 380,900 gpm to 386,000 gpm. This revision was necessary to correct a deficiency noted in the original cycle analyses involving the locked reactor coolant pump rotor.

This issue has been placed in our corrective action program.

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

Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station Attachments: 1) Byron Station, Unit 1 Cycle 12, COLR, Revision 3

2) Byron Station, Unit 2 Cycle 11, COLR, Revision 1 RPUJL/rah cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager- NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

Attachment I Byron Station, Unit 1 Cycle 12, COLR, Revision 3

<- - - 4d CAC-02-34, Rev 2 CAC-02-34, Rev 2I

.~~~~~~~~~~~~~~ I CORE OPERATING LIMITS REPORT (COLR)

F

FOR

-BYRON UNIT I CYCLE 12 I

Revision 3 I

. , .~~~~~~~~~~~~~~~

I A BNFL Group company

CAC-02-34, Rev. 2 no__ % - -

ragevu or o CORE OPERAING UMITS REPORT (coLR) for BYRON UNIT 1CYCLE 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 12 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 Safely Limits (Sls)

LCO 3.1.1 Shutdown Margin (SDM)

LCO 3.1.3 Moderator Temperature Coefficient (MTCY LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Ba'nk 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 (F'4 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)

LO 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 TCO 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)

.ol - I CAC-02-34, Rev. 2 Page 2 of 16 CORE OPERATING UMITS REPORT (COIR) for BYRON UNIT 1 CYCLE 12 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 SaevLirnnsfSLs) (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 exceedthe liits specified in Figure 2.1.1.

680 660 2471 1p1"i1'a LA.-

C" 2250 ps.

. W, 640 L

0)

Ak E

I 620 _0 __ \i\

690 580 Froclion of Nominol Power:

Figure 2.1.1: Reactor Core Limits

CAC-02-34, Rev. 2 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 2.2 Shutdown Marain (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 (tCOs 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 lo 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 BOIJARO/HZP-MTC upper limit shafl be +2.11 x I 5Ak/cF.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10 4Ak/k/oF.

2-3.3 The EOIJAROIHFP-MTC Surveillance limit at 300 ppm shall be

-3.7 x 104 6k/WoF ,

-2.3.4 The EOIJARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10 AkkoF.

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 Ufe 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 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 113 Step overlap limit.

CAC-02-34, Rev. 2 I

I Page 4 of 16 CORE OPERATING LIMITS REPORT (COLP) for BYRON UNIT 1 CYCLE 12

. .. .~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

gure2 5.1:

i Control Bank nertion Units Versus Prcerd Rated Tllmd Ib P I 224 (24 q 224) CfNq 224) . f 20 c

SI 160 (1000@/ 161)

'1 m

B 10 4-0

=0.100 0

0 je 0 a:o 0 10 20 30 40 5 60 70 80 90 100 Pelative Pawu (Per~ert)

CAC-02-34, Rev. 2 Poge 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 2.6 Heat Flux Hot Channel Factor Fag)) (LCO 3.2.1) 2.6.1 Ftl FQ(Z) < xK(Z) forPO0.5 0.5 FQ(Z) < - xK(Z) forP>0.5 P

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

.t The normal operation W(Z) values have been determined at burnups of 1737, 6000,14000, and 20000 MWDtMTU.

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 FWo(z) as per Surveillance Requirement 3.2.12. A 2% penalty factor shall be used at an cycle bumups that 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 be calculated by the following formula U, =U

  • J where:

Uw = Base FQ measurement uncertainty 1.05 when PDMS is inoperable.

(U. is defined by PDMS when operable.)

Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

FQ(Z) Warning Setpoint > 211% of Fo:Z) Margin FQ(Z) Alarm Setpoint >0% of Fo(Z) Margin

4.

CAC-02-34, Rev. 2

, Page 6 of 16 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1CYCLE 12 Figure 2.6.1 K(Z) - Normalized Fo(Z) as a Function of Core Height (0.0 1.0) 6010

,0.924) .

0.9 0.8 0

0.7 IL 10 0.6 0

0.5' z

N 0.4~ LOCA Limiting

-4

- Envelope 0.3 0.2 - - - - - - --

0.1 I - - -- - --

0'-

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

.1i CAC-02-34, Rev. 2 f Page 7 of 16 CORE OPERATING LIMITS REPORT (cOlR) for BYRON UNIT 1CYCLE 12 Hsit MACWU)

Fsd ytcn ril CQ1012 000 L.oo0 0.20 LOW0 Fle2.&2.o 0.40 1.0000 0.60 3.0000 - Sumny dWQZ)FwdnOd 1737 NWDMAU 0.80 1.0000 (-cponRctfamlS% EXdUI£0 WCAP-10216) 1.0 1.0000 1120 1.0000 IAO L.000 1.60 L.oom 1.40 1.60 1.1111 2.00 1.0999 2.20 1.0636 IM~i 1L1 .I 2.60 1.0742 2.6 1.0743 1.0753 1.35

, .2gW~t 3.O0 3.20 1.0762 3.40 1.0733 3.60 3.0302 3850 1.0311 ,

4.00 1.0630  : 1 410 1.0334 L.037 tao 4.40 4.60 1.0631 4.80 8.o t.0837 Ilemo 1.2293

.a o 5600 1.033 20 l.0941 i 5.40 1.0993 540 3.3073'  !

6.o 6120 6.40 1.3340 1.1447 1.1529 0

z (1

FF~tI0;14 I

6.60 1.1596 6.80 1.1661 7 o 1.1755 ¢ 1.20 720 3.1331 7AO L.IM9 7.60 7 .80 8.20 6.40 12073 1 2173 1.2422 32523 1.15

. L r L +/- J L1 i *-3 w 8.60 1.2436 83m0 1.2711 9.00 9.20 9.40 12937 1.3135 1.3219 I.

9.60 1.3390 1.10 9.80 1.3493 10100 1.3558 1420 1.3764 40 1.0000 10.60 1.000 10180 3.000 DOi 1100 3.0000

  • 1.05 11.20 2.000w 0.00 2.00 4.00 6.00 8.00 10.00 12.0

))AO 3.0000 CORE HEIGHT (FEET) 1160 1.0000 11.80 .l00 12.00 3.0000

CAC-02-34, Rev. 2 9 ^

I I, Page8of 16 CORE OPERATING LIMITS REPORT (coR) for BYRON UNIT CYCLE 12

.~~ I ~

HdVi. MAX WQZ)

Feet - ByrcnUrlI d 12 0.0D I.000o 0.20 100 - - . Fge2.6.2.b -

040 1.0000 Q60 1.4000 *SuwydWa)Futcocd 6000 M*NDA* U 0.80 l.0000 ( qpcr tarl 15% Eaudsdpw VW-P216)

.00 10000 1.20 I.0C00 . i 1.40 IAOO0 1.hO l.ODOO

  • 1.45 1.80 1.1300 2.00 1.1I88 2.20 1.1056 i 2.40 1.I99, 11 2.60 1.0935 t.40 I

zo 1.0sll 3.00 3.20' 3.40 3.60 1.0919 1.0930 1.0935 1.0919 i M~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ I i

3.80 1.0919 i 4.CO l.0909 130 4.20 .0385 I 4.40 1.0349 I i

4.60 1.079F 4.80 1.0161 s.m 1.0717 t.30 II 5.20 1.0212 I SAO I.O4 1

. t , _I e ~ i 4 ..

__1-t 4~ -r

.E - i 5.60 1.0858 2 S.80 1.0955 0 6.00 1.1037 6.20 1.1202 z 1.25 I

i 6.40 1.1319 6.60 1.141g 1.1515 II 6.h0 7.O .1623 I 7.20 1.1770 7.40 1.19D6 1.20 7.0 1.2014 7.80 1.2127 8.00 12316 8.20 1.2336 8.40 - I234 a.8o 8.80 9.00 9.20 9.40 12901 13063 13240 13413 13571 1.15 2_L f t; _+ rn-I -4..4  ! -

9.60 13705 9.80 1342 1.10 10.00 13956 1l20 1.4111 10.40 1.0000 1L60 .0000 10.80 l.000D 11.00 I.000D 11.20 I.OXO0 0.00 2.00 4.00 6.00 8.00 10.OD 12.00 11AO 1.000D CORE HEIGHT (FEET) 11.60 1.0000 11.80 .0000 12.00 3.ODO

CAC-02-34, Rev. 2 I , - Page 9 of 16 CORE OPERAlING UMITS REPORT (COUZ) for BYRON UNIT 1CYCLE 12 HdM MA(w CZ)

F4 I1 Ce ByronUrit 12 0.00 tiom 0.20 FW9e2.6.c 1.000 0.40 Sunryd WZ)Fuxdcnc 14000 VMDA9 U 0.60 1.000 0.80 (Im"Bcrt5% Excudcip~VY.AP-10216)

IAM 1.0000 3.20 1Q40 l.60 1I35 1.80 1.3097 2.00 2.20 1.2636 2A0 1.2S31 2.60 1.2389 2.80 12274 3.CO 12133 3.20 *1.193 3.4qt 3.133

, 3.80 1.1744 4.CO 1.1662 4.20 1.1576 4.40 1.1473 4.60 1.1333 4.80 1.1240 500 1.3206 520 1.1.164 54.0 1.1 140 660 3.1303 580 1.1053 60 1.3130 I 6.20 1.1212 6.40 1.1277 lon 6.60 6.80 7.CO 7.20 1.1323 1.1363 1.1432

'a 0jJ tN-1.0i 4 X 740 1.1440 7.60 1.1432 7.80 8.00 8.20 1.1423 3.1400 1.1374 1Q5 I.

8.40 1.1346 8.60 1.1313 8.80 1.1335 9.00 5)1343 9.20 1.1344 9AG 1.1391 9.60 1.1438 9e8 1.1412 10.00 1.1689 10.20 1.1964 l040 3.0000 10.60 3.0000 1804 1.0000 11.00 3.0000 11.20 0.00 2.00 4.00 6.00 8.00 10.00 12.00 1.0000 11.40 1.0000 CORE HEIGHT (FEET) 11.60 1180 1.0000 12.0D

l CAC-02-34, Rev. 2

,

  • Page 10 of 16 CORE OPERATING UMITS REPORT (COQ) for BYRON UNIT 1CYCLE. 12

. I I

.~~~~~~~~~~~~

ByronUril I CWe 12 0.00 i.Otoo 00 2.000 figve2.62.d 0.40 1.0000 0.60 IMPo Sutnry d W) F aclk20000 M#VDM U 0.80 1.0000 f Crcpaid lSBdl57Exducbdrs WCAP-0216) 1.00 I20000 1.20 1.000o 2. , i 1.40 1.0000, Ia IA0 I.00o 1.80 2.00 127t7 1.26S6 I, 2.20 1.2546 2.40 . 1.2420. I 1.2257 2.60 2.80 1.2116 o~~~~1 '+/-1 iL.

300 2006 3.20 ' .ltt2 I l3a 3.40 3.60 3.80 4.00 I.177t 1.1739 1.1726 1.1705 s~~ 4.iikWiLvv .

i 420 2.1677 I

4.40 1.1629 4.60 1-1577 1.1624 i.25 4.80 5,00 1.1663 5.20 1.1675 5.40 5.60 1.1691 1.1797 )~~~~~~~... .L ' 4...fi f

S80 1.1949 0 6.O 1.2087 6.20 12196 120

§ 6,40 1.2276 6.60 1.2316 6.80 1.2333 7.00 1.2330 7.20 12283 I 7.40 1.2236 tt~~~~~~~~~

7.60 1.2147 70 1.2060 1.25 8.00 1.1940 820 *1.790 8.D 1.1636 8.60 1.1448 8.80 1.1270 9.0D 1.1349

.20 1.1143 9.40 1.1154 1.0 9.t0 1.1442 9.80 2.2833 10.00 12154 10.20 12481 10.40 1.0000 10.60 1.0000 10.80 .0000 11.00 .0000 i nr

  • f.0 11.20 .0000 2.00 4.00 6.00 8.00 10.00 12.00 0.09 11.40 .0000 CORE HEIGHT (FEET)

L60 .0OWo 11.80 1.0000 12.00 1.0000

CAC-02-34, Rev. 2 I

Page 11 of 16 CORE OPERATING LMITS REPORT (CoIR) for BYRON UNIT 1 CYCLE 12 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor - Fo(z)

(MWD/MTU) (O) 837 2.00 1009 2.78 1524 3.76 1695 3.90 1867 3.91 2039 3.81 2554 3.33 2726 3.33 2897 3.47 3584 4.67 3756 4.76 3928 4.66 4786 2.09 4958 2.00 13716 2.00

, -14231- 2.67 14402 2.75 14574 2.75 14746 2.66 15433 2.00 Notes:

Linear interpolation Is adequate for intermediate cycle burnups.

All cycle burnups outside the range of the table shall use a 20/a penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

CAC-02-34, Rev. 2 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNSl (LCO 3.2.2) 2.7.1 FH 5< 0,H l.O + PF 6,H(1.0- P)l where: P the ratio of THERMAL POWER to RATED THERMAL POWER 1:.p1.70 PF&H =0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UF,,H. lo be applied to the Nuclear Enthalpy Rise Hot Channel Factor Fm Nshall be calculated by the following formula:

UFAH = F,*l where:  :

US,_ Base F,,m measurement uncertainty 1.04 2.7.3 PDMS Alarms:

F H Warning Setpoint 2 2% of F"hH Margin FH Alarm Selpoint 2 0% of FNdH 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 PDMS Surveillance Reporl, whichever is more conservative.

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

2.9 Departure from Nucleate Boilino Ratio (DNBR) (LCO 3.2-5) 2.9.1 DNBRAPsL Ž 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 0% of DNBR Margin

LAL-U--34, Ke6. 2 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Therrmal Power Axal Flux Difference Lmits I z z

wth PDM Inoperable i

I 120 ~~'4 _

. 80 -

-50 4-0 20 -10 0 10 20 30 40 50

~~~~~~~~~*-.

AAL FLUXF SCFE (n

CAC-02-34, Rev. 2 Page 14 of 16 CORE OPERATING MITS REPORT (CXR) for BYRON UNIT 1 CYCLE 12 aT Setpoint 2.10 Reactor Trip System RTS) Instrumentation LCO 3.3.1 - Overtemperature Parameter Values 2.10.1 The Overlemperature AT reactor trip setpoint K1 shall be equal to 1.325.

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

be 2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall equal to 0.00181/ psi.

588.0 oF.

2.10.4 The nominal Tars at RTP (indicated) T, shall be less than or equal to psig.

2.10.5 The nominal RCS operating pressure (indicated) P' shall be qual to 223~

to 2.10.6 The measured reactor vessel AT lead/lag time constant ri shall be equal 8 sec.

to 2.10.7 The measured reactor vessel AT lead/lag time constant c2 shall be equal 3 sec.

or equal 2.10.8 The measured reactor vessel AT lag time constant U3shail be less than to 2 sec.

The measured reactor vessel average temperature lead/lag time constant 4

2.10.9 shall be equal to 33 sec.

1 2.10.10 The measured reactor vessel average temperature lead/lag time constant shall be equal to 4 sec.

r6 shall be 2.10.11 The measured reactor vessel average temperature lag time constant less than or equal to 2 sec.

2.10.12 The 1 al) positive' breakpoint shall be +10%,l.

2.10.13 The f (al) "negative" breakpoint shall be -18% Al.

2.10.14 The f (Al) positive slope shall be +3.47% % AlI 2.10.15 The f (I) negative" slope shall be -2.61% / % Al.

16 CAC-02-34, Rev. 2 Page 15of 16 12 CORE OPERATING UMITS REPORT (cOLQ) for BYRON UNIT 1 CYCLE AT Setpoint 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower Parameter Values 2.11.1 The Overpower AT reactor trip selpoint K4 shall be equal to 1.072.

be equal 2.11.2 The Overpower AT reactor trip setpoint Tvg rate/ag coefficient K5 shall to 0.02/ °F for increasing T.v.

Ks shall be equal 2.11.3 The Overpower AT reactor trip setpoint Tn rate/lag coefficient to 0/ F for decreasing Tavg.

shall be equal 2.11.4 The Overpower AT reactor trip setpoint T8 g heatup coefficient Kr to 0.002451 oF when T > Tn.

equal 2.11.5 The Overpower AT reactor trip selpoint T.,, healup coefficient 1K6 shall be

- to 0 IoF when T < T,.

to 588.0 -F.

2.11l.6 The nominal Tg at RTP (indicated) T, shall be less than or equal The measured reactor vessel AT lead/lag time constant tr shall be equal to 2.11.7 8 sec.

be equal to 2.11.8 The measured reactor vessel AT lead/lag time constant x2 shall 3sec.

less than or equal 2.11.9 The measured reactor vessel AT lag time constant Tshall be lo 2 sec.

r shall be 2.11.10 The measured reactor vessel average temperature lag time constant less than or equal to 2 sec.

constant r7 2.11.11 The measured reactor vessel average temperature rale/lag time shall be equal to 10 sec.

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

2.11.13 The f2 (Al) negaive' 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.,

CAC-02-34, Rev 2 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 12 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 (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 1756 ppm (LCO 3.9.1). ,

2.13.4 The Reactor Coolant System boron concentration shall be greater than or equal to 1831 ppm prior to initial criticality of Cycle 12, or greater than or equal to 2042 ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3.1.g and 3.1.k).

A BNFL Group company

Attachment 2 Byron Station, Unit 2 Cycle 11, COLR, Revision 1

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 11 REVISION 1

BY2C I I COLR, Rev. I I

Page I or i6 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 11 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,)

LCO 3.2.3 Axial Flux Difference (AFO)

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 (BOPS)

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 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)

BY2C.1 I COLR, Rev. I Page2 o 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 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.

I 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.

680 I

- 2471 psia 660 LU-a>

L.,

. G> 6 4 0 C)

Q IE J +/- L LL\PS U) 620 0

crb Q>

600

_'~~to I\l\

580 .,.

0 2 4 .6 . 1.2 Fraction of Nominol Power Figure 2.1.1: Reactor Core Limits

BY2CI I COLR, Rev. I Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYEN UNIT 2 CYCLE I 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, 3.1.1, 3.1.h, and 3.1.j).

The SDM limit for MODE 5 is:

2.2.2 SDM shall be greater han 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 TemDerature Coefficient MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOLARO/HZP-MTC upper limit shall be +2.72 x 1O Ak/k/OF.

2.3.? The EOUAROIHFP-MTC lower limi shall be -4.6 x 10 Ak/k/0 F.

2.3.3 The EOUAROIHFP-MTC Surveillance limit at 300 pprn shall be

-3.7 x 10'4 AWk/lF.

2.3.4 The EOVARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10- ak/kf0 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 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 a 113 Step overlap limit.

BY2CII COLR, Rev.I Page4of16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II Figure25.1 Contr Bar* lnrtsion Unit Versus PArcerd fted ThemW

-Poie (27V1q 224) (77/3 224) 180 X

3 2 (a411 lI ilT

.L.

- I 140 0

0.

It . 0*

f I120 +...- --

c 0

100 a-0 m

m

.IX0 0 10 20 30 40 50 60 70 80 90 100 RMative Power (Pmt)

BY2C II COLR, Rev. I Page of 16 CORE OPERATIN4G LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I 2.6 Heat Flux Hot Channel Factor (Fn(Z) (LCO 3.2.1) - ,

2.6.1 Total Peaking Factor:

FQ (Z) Q- xK(Z) for P < 0.5 . -

0.5

- co~RTP FQ(Z) * -xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER 1F7""p 2.60 I K(Z) is provided in Figure 2.6.1.

2.6,Z 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 MWD/MTU.

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 Fo(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.

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:

UFQ U OU.

where:

Uqu = Base FO 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:

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

BY2C I I COLR, Rev. I CORE OEANGMTREOTCL)orYRNUT2Page 6 of 16 CORE OPERATING LIMITS REioRT (COLOR) for BYRON UNIT 2 CYCLE I11 Figure 2.6.1 K(Z) - Normalized Fo(k) as a Function of Core Height 1.

(0.0 1.0) 6.0 _

,0.924)

  • 0.

0.

I I u.

o 0.

=

.4 . ,,-SILOCA Limiting' Enveloe 0.

.3~~~~~~~~~~~T .. _I_ P.

O..2 .-

0..1-'

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

BY2CI I COLR, Rev. I Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BY1,ON UNIT 2 CYCLE II Heit MX WQ)

Feet ByorvUnt2Cyde 11 0.00 1.0000 0.20 1.0000 ' Figxe2.6.2.o 0.40 1.0000 0.60 1.0000 SuaycfW(Z)F0cS 1ctI50A04IT 0.80 1.0000 (1cpcndB0tbi5%Exdt e WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 ,41.0000 1.3S 1.80 L.Zl23 I 2.00 1.1939 2.20 1.1773 2.40 1.1617 2.60 1.1456 2.80 3.00 1.1373 3.20 1.1357 1.30 3.40 1.1328 Trr~~~I-L. '- I:1 . + L 3.60 1.1296 i

3.80 4.00 1.1322 1.1337  ;]  !< *, ' . -t '-

  • i,_, _

i 4.20 1.1362 4.40 1.1366 4.60 1.1371 i-4.80 1.1357 1.25 500 5.20 1.1344 1.1310 k~~~. -tli i A

i t_>

5.40 5.60 5.80 1.1266 I.1305 1.1361 z III- Irl,___. ,14a  !.

6.00 1.1417 0 6.20 1.1521 z

6.40 T.1619 Z 1.20 M. S i  ! .__.t li_4. .---- -- 4 6.60 1.1707 iz.

6.80 1.17S5  : } }_ ' . 1._!.... ' _,.__.

  • f- .'.' .

7.00 1.1846 7.20 1.1896 7.40 1.1942 7.60 1.1987 i 7.80 1.2070 i 1.15 8.0D 1.2137 I 8.20 1.2174 8.40 1.2221 I -.- !-1 _ .i. ~~~* t- ...

8.60 8.80 1.2273 1.2353 I t i !I  ! t !T._

I 9.00 1.2455 9.20 1.2564 II i

9.40 1.2677 I I

9.60 1.2783 9.80 1.2816 I 1.1: I 10.00 1.2777 j:

10.20 1.2736 i 10.40 1.0000 .o 10.60 1.0000, i 10.80 I.0000 I 11.00 1.0000 _

11.20 1.0000 .00 2.00 4.00 6.00 8.00 10.00 12.00 -

IIA0 1.0000 11.60 I.oO CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

BY2C I I COLR, Rev. I Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 Hel9Va MAX W(Z)

Feed yronUrit 2 Cycle 11 0.00 30000 0.20 1.0000 F Wge 2.6.2.b 0.40 LOW0 060 1.0000 -*- S uTrwny d WQ) Fuxtin ct 6000 MVDM U 0.80 L.0000 CFcpxBdca, 15% Exdt pr WCAP.10216) 1.0000 1.20 1.0000 1.40 '1.0000 1.60 1.0000 1.35 1.80 .1998 II 2.0D 1.1853 II 2.20 1.1698 i

2.40 1.1552 2.60 1.1400 I 2.80, 1.1303 I 3.00 1.1267 3.20 1.1214 130 3.40 1.1161 . .t im t J t 4 It v t 3.60 1.1089 1.1069 . X Xi~ S. i 3.80 4.00 I.1065 I

'4.20 1.1041 i 4.40 1.1026

£_4 _ .,-;' i.__.

4.60 1.l018 1.0993 125 4.80 5.00 1.0965 1.0916

. 3- 1 V _ i ,. I-.. ,.I+

I 5.20 5.40 1.0170 5.60  !.8l8  :' i 5.80' 6.00 1.0S5S 1.09B4 z  :

I ii zft .'t 6.20 1.1181 . I

!- 1.20 6.40 6.60 6.80 7.00 1.1357 1.1516 1.1664 1.1802 P

t H _ l -, i p

7.20 1.1928 7.40 7.60 7.0 1.205B 1.215t 1.2258 1.15 j 1 Ftt -

1it! 2 8.0D 1.2339 1II 8.20 1.2409 8.40 1.2479 I 8.60 1.2509 I 8.80 1.2593 9.00 1.2676 .~4 W l.S;3 .,., I 9.20 1.2751 .i 9.40 1.2833 1.0 14 _. a~

I 9.60 1.2937 a -- t-- 4-It 9.80 1.3056 10.00 1.3173 I020 1.3267 1. 1.0 10.40 1.0000 10.60 1.0000 10.60 1.0000 i C 11.00 1.0000 11.20 1.0000 0.00 2.00 4.00 6.00 8. DO lO.O 12.00 11.40 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 1.0000 12.00 1.0000

BY2CI I COLR, Rev. I Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II Heit MAXW)

Feet Bypn Urit 2 Cyde 11 0.00 1.0000 0.20 1.0000 F Wge2.6.2.c 0.40 .0000 0.60 1.0000 SuyrCry d WQ)FFundlcn d 14000 MWDM u .

0.80 1.0000 CcopudBllan 15% Exdudedper WCAP-10216) 1.00 10000

_ ____L.~~~~~~~~~~~~

1.20 1.0000 1.40 1.0000 1.60 4.0000 1.35 1.80 1.210 2.00 1.2520 I.

2.20 1-U400 4

2.40 1.229S 2.60 1.2204 2.80 1.2133 3.00 1.2047 3.20 I.1943 1.30 3.40 1.145 3.69 1.1722 3.80 1.166S 400 1.1639 4.20 1.123 4.40 1.1534 4.60 1.1470 4.80 1.1396 125 5.00 1.1319 5.20 1.1225 5.40 1.1248 5.60 5.80 6.00 6.20 1.1274 1.2 1.1296 1:1272 z

0 0

z, 1.20 I

6.40 1.1248 i 6.60 6.80 1.1197 1.1145 3 I 1 7.00 1.1176 7.20 1.1236 7.40 1.1305 7.60 1.1346 7.80 1.1386 1.15 I i

8.00 1.1417 8.20 1!1429 8.40 1.1430 8.60 1.1443 8.80 1.1464 9.00 1.1475 9.20 1.1515 9.A0 1.1566 1.10 9.60 1.1643 9.80 1.1700 10.00 1.1755 10.20 1.2002 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000  !.I 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 II40 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 1.0000 12.00 1.0000

I BY2C 11 CQLR, Rev.

BY29C I I COLR, Rev. Page 0 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE Hegt m<(wo)

Feel Bycn Urit 2Cyde I1I a(XJ 1.0000 0.20 1.0000 Figpe2.6.2.d

-040 1.0000 0.60 1.0000 SuivrE~ d~WQ) Fvtrd 2000 MOMvt U 0.80 1.0000 (Tcpa Bof~t 15% E xduW p WCAP- 10216) 1.00 I.Oo 120 1.0000 i 1.40 41.0000 I

1.60 1.0000 1.35 I' I 1.80 1.2735 2.00 2.20 3.2630 1.2487 I *.i.-.-

3';

'3J. tI I:

2.40 1.2352 2.60 3.2171 2.80 1.2027 a I I*

3.00 1.1S74 I' 3.20 1.1715 I 1.30 I' I I

  • I 3.40 1.1703 L 4-'--.

3.60 1.1686 I

1* i L4.

i .,

I I J

I 3.80 4.00 1.1669 1.1637 I -tH 1tL 4

I 4.20 1.1611 i '3 4.40 4.60 1.1651 1.1742 Ii 1.?5 I I I _____ I 4.80 1.1S14 a 3 -I--

.A. .-... & i 5.00 1.1g57 -- -

5.20 5.40 .

1.1398 1.1933 Ii II 5.60 .1939 i

  • 1 z 3 3 1
  • 5.80 1.1925 0 6.00 1.190 i F -T * -

6.20 1.1826 i Uz, 120 1" - i 6.40 1.1787 4-6.60 1.1375 i IL L. .

6.80 1.l938 7.00 1.1991 i

7.20 1.2019 II 4 7.40 1.2027 3 1 7.60 1.2007 ---= F1 I I 7.80 1.1981 1.15 8.00 1.1936 -'- 3 8.20 1.148 8.40 1.1777 -i I 8.60 1.1674 -1 I ,

8.80 1.1570 a I 9.00 1.1494 1 I 9.20 1.1467

J I'
  • -1 i*

I I ________

II 9.40 9.60 1.1478 1.1690 I.10 j 1.1' i ii 9.80 1.2070 I I-I-.

F' I i

10.00 1.2410 10.20 1.2710 I -- '-I..--

104 1.0000 -A 10.60 1.0000 4 I

10.80 1.0000 j

II05 U:

1.00 1.0000 f 11.20 1.0000 i 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 I.0000 I - CORE HEIGHT (FEET) 11.60 I.0000 11.80 1.0000 12.00 l.OOm

. - W BY2CI COLR, Rev. Page 11 of 16 CORE OPERATING LIMITS REPORT (C.OLR) for BYRON UNIT 2 CYCLE 11 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor -F~o(z)

(MWDIMTU) 322 ._2.00

.493 ___ 2.55 I I 665 2.74 837 2.76 f 1008 ._2.74 I-1866 , 2.58 2210 _2.58

-2896 - 2.74

_ - 3068 . } 2.75 3239 _ _ - -- 2.72 3411 0 2.65 3754- -- 7 - 2.30 4097 2.00 11821 . 2.00 11992 2.11 12335 2.84 12507. 2.89 12679 2.87 12850 2.71 13537 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 the 3.2.1.2 Surveillance Requirements. I

41 BY2C I1COLR, Rev. Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I I 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F'AHI (LCO 3.2.2) 2.7.1 F FRTP dl.O+ PFH(l.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F TPH = 1.70 PF^H = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFmH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F1 shall be calculated by the following formula:

UFaH = UFHm where:

UF6H, = Base F ,mmeasurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FN H Warning Setpoint 2 2%of FrH Margin FN ," 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 FLU)( DIFFERENCE (AFD) Acceptable Operation Limits 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 Devarture from Nucleate Boiling Ratio (DNBR (CO 3.2.5) 2.9.1 DNBRApsL 21.536 The Axial Power Shape Umiting DNBR (DNBRAPS) 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

BY2C I I COLR, Rev. I Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Ada Flux fference Units i with PDS lrperable I q

i i

I

! 120 'I A-.. 4IA' .~

.I 0

i 2504030-20-100 1020304050

~~~~~~~AA RM AL EF ENCE (/4

BY2C ICOLR, Rev. I Page 14 of IC0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I 2.10 Reactor Trio System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Selpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K1shall be equal to 1.325.

2.10.2 The Overlemperature AT reactor trip setpdint T coefficient K2 shall be equal to 0.0297 1 F.

2.10.3 The Overtemperature At reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 Ipsi.

2.10.4 The nominal T,. at RTP (indicated) T' shall be less than or equal lo 588.0 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 r1 shall be equal to 8 sec.

2.10.7 The measured reactor vessel AT leadlag time constant r2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel AT lag time constant c3 shafl be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant T4 shall be equal to 33 sec.

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

2.10.11 The measured reactor vessel average temperature lag time constant Mtashall be less than or equal lo 2 sec.

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

2.10.13 The f1(Al) negative- breakpoint shall be -18% Al.

2.10.14 The t1 (Al) positive' slope shalt be +3.47% 1% Al.

2.10.15 The (Al) negative slope shall be -2.61% 1% Al.

BY2C II COLR, Rev. I Page IS of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I 2.11 Reactor Trid System (RTS). Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter 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 T.,, rate/lag coefficient K5 shall be equal to 0.02 / F for increasing T..

2.11.3 The Overpower AT reactor trip setpoint Tag ratd/lag coefficient Ks shall be equal to 0 1 F for decreasing Ta 2.11.4 The Overpower AT reactor trip seipoint T.gheatup coefficient K6 shall be equal to 0.00245/ F when T>Tr. al be equal 2.11.5 The Overpower AT reactor trip setpoint Tv heatup coefficient K6 shall be equal toO/*FwhenT T". .

2.11.6 The nominal Tao 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 tx shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant T2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel AT lag time constant r3shall 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 To shall be equal to 10 sec.

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

2.11.13 The 2 (Al) negative' breakpoint shall be 0 for all Al.

2.11.14 The 2 (Al) positive' slope shall be 0 for all Al.

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

BY2CI I COLR, Rev. I Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYIAON UNIT 2 CYCLE 11 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 (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 1753 ppm (LCO 3.9.1).

2.13.2 The Reactor Coolant System boron concentration, with all shutdown and control rods fully withdrawn, shall be greater than or equal to 1803 ppm prior to initial criticality of Cycle 11, or greater than or equal to 2048 ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3.1.g and 3.1.k).

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