BYRON 2005-0037, Cycle 14 Core Operating Limits Report

From kanterella
Jump to navigation Jump to search
Cycle 14 Core Operating Limits Report
ML050910138
Person / Time
Site: Byron Constellation icon.png
Issue date: 03/23/2005
From: Kuczynski S
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.01.0700, BYRON 2005-0037
Download: ML050910138 (37)
v • d • e


Text

Exekrn S.

Exelon Generation Company, LLC Byron Station 4450 North German Church Road Byron. IL 61010-9794 www.exeloncorp.com Nuclear March 23, 2005 LTR:

File:

BYRON 2005-0037 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454

Subject:

Byron Station Unit 1 Cycle 14 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

we are submitting the Unit 1 Cycle 14 COLR Revision 1 and Revision 2. Revision 1 was issued to address the fuel reload period of Cycle 14. Revision 2 was issued to incorporate the effects of the core redesign resulting from the discovery of fuel failures in fuel originally planned for use in Cycle 14. Note that Revision 0 of the Unit 1 Cycle 14 COLR was never issued.

Should you have any questions concerning these reports, please contact William Grundmann, Regulatory Assurance Manager, at (815) 234-5441, extension 2800.

Respectfully, 594 7,t`

Stephen E Kuczynski Site Vice President Byron Nuclear Generating Station Attachments: 1) Byron Station Unit 1 Cycle 14 COLR, Revision 1

2) Byron Station Unit 1 Cycle 14 COLR, Revision 2 RPUJLAjs cc:

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

  1. wI)

I

ATTACHMENT 1 Byron Station Unit 1 Cycle 14 Core Operating Limits Report Revision 1

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 14 (REVISION 1)

Revision I Pagec I oi 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 14 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 (FMAH)

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 (FTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)

LCO 3.4.1 Reactor Coolant System (ACS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the TRM TLCO 3.1.b TRM TLCO 3.1.d TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.i TRM TLCO 3.1.j TRM TLCO 3.1.k Technical Requirements Manual affected by this report are listed below:

Boration Flow Paths - Operating Charging Pumps - Operating Borated Water Sources - Operating Position Indication System - Shutdown Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff 2 1.0 Shutdown Margin (SDM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)

Revision I Page 2 of 16 CORE OPERATING LIMITS REPORT (COI.R) for BYRON UNIT I CYCLE 14 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.

680 660 U-0' a)

I-- 62 0 a,

03 600 580 247 psi1 225 psi

\\_

\\_I

.2 1

. 6

-l 8 l

2 Fraction of Nominal Power Figure 2.1.11: Reactor Core Limits

Revision I Paoc 3 or 16 CORE OPERATING LIMITS REPORT (COLR) Ifr BYRON UNIT I CYCLE 14 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.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOUARO/HZP-MTC upper limit shall be +1.79 x 10 5 Ak/k/ 0F.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 104 AkW/kF.

2.3.3 The EOIJARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10 4 Ak/k/rF.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 AkIk/1F.

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

Revision I 224 220 200 180 3 160 1-W 140 0u us 120 0.

0 100 co Cr 40 20 0

Pagec 4 sol 1 6 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Figure 25.1:

Control Bank Insertion Ulmits Versus Percent Rated Thermal Power (26.520/, 224)

(76.96/, 224)

BAN XB (100%/.,161) 0 10 20 30 40 50 60 70 Relative Power (Percent) 80 90 100

Revision I RPac 5 of 16 CORE OPERATING LIMITS RLPORT (COLR) lor BYRON UNIT I CYCLE 14 2.6 Heat Flux Hot Channel Factor (Fig (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FRlIl FQ (Z) < 0* 5 xK(Z) for P < 0.5 0.5P FQ(Z) < P xK(Z) forP>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER RTP F0"

= 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 MWD/MTU.

Table 2.6.2 shows the Fco(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWa(z) as per Surveillanbe Re'4uirernent 3.2.1.22. A 2% penalty facto; 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 Fa(Z) shall be calculated by the following formula U/,Q = U.".

  • U, where:

Uqu = Base F0 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 F0(Z) Margin FO(Z) Alarm Setpoint 2 0% of FO(Z) Margin

Re~vision i Pa-e 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Figure 2.6.1 K(Z) - Normalized F0(Z) as a Function of Core Height 1.1 1

0.9 0.8 "i 0.7 0

L

° 0.6 as 0.5 z

X 0.4 0.3 0.2 0.1 0

(0.0 1.0) 11 1

11)

LOCA Limiting E

_E__elope

,0.924) 0 1

2 3

4 5

6 7

8 9

10 11 12 BOTTOM Core Height (ft)

TOP

Revision I Page 7 oh16 CORE OPERATING LIMITS REPORT (COLR) lor BYRON UNIT I CYCLE 14 Height Feet 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00, 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 1020 10.40 10.60 10.80 11.00 1120 11.40 11.60 11.80 12.00 MAX W(Z) 1.(0x0)

I.tW)t I.0(X)O I.11X)

L.4)0X)

I 04O)

I.o(x)o I (8100 I txXX) 1.233.

1.2290 1.2114 1.1952 1.1772 I.1638 1.1520 1.1458 1.1399 1.1339 1.1280 1.1226 1.1222 1.1216 1.1211 1.1195 1.1169 1.1133 1.1097 1.10(1 1.I(M40 I. 1096 1.1229 1.1377 1.10) 1.1638 1.1750 1.1872 1.1967 1.2063 1.2131 1.2181 1.7223 1.2246 1.2269 1.2264 1.2242 1.2286 1.2279 1.231S 1.2295 1.2243 1.229)t I.1X81()

I.tKXX)

I.(XX8)

IO.W88)

I.(1XK)

I.110x) 1.048X)

I.04884 1.041W Byron Unit 1 Cycle 14 Figure 2.6.2.a Summary of W(Z) Function at 150 MWDIMTU (Top and Botom 15% Excluded per WCAP-t 0216) 1.35 1.30 1.25 z0 C,

S 1.20 U.

3.

1.15 1.10 7[7

.i.1 1:

[44 j

4 I.

V

.05 0.00 2.00 4.00 6.00 8.00 10.00 12.00 CORE HEIGHT (FEET)

Revision I Page 8 of, 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Height Feet 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1A0 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 1020 10A0 10.60 10.80 11.00 1120 tIA0 11.60 11.60 12.00 MAX W(Z)

I.tX x)O 1.(yxxJ It.(xxx)

I.188)0P 1.(X)00 1.01000 1.2084

1. I'10 1.1732 1.1585 1.1457 1.1421 1.1384 1.1328 1.1272 1.1198 1.1168 1.1147 1.1128 1.119 1.lt068 1.10.19 1.0999 1.0948 I.0MX 1.0856 1.0864 1.0'391 1.10I 1.1277 1.144 1.1622 1.1770 1.1918 1.2()47 1.214J 1.2245 1.2325 1.23X6 1.2477 1.2558 1.264) 1.2734 1,2K24 1.2956 1.3068 1.3179 1.3291 1.3374 I 1.88) 1081()

I (BM88)

I IXHXI 1.0X0X0 1.(XXX) t.0XXX) 1.1t)XI 1IXX11 Byron Unit I Cycle 14 Figure 2.6.2.b Summary of W(Z) Function at 6000 MWD/MTU (Top and Bottom I 5% Excluded per WCAP-10216) 1.35 1.30 1.25 z0 P

z 1.20 IL 1.15 1.10

.1.1' I.

  • 1

9 I

4

I 1 n0 0.00 2.00 4.00 6.00 8.00 10.00 12.00

° CORE HEIGHT (FEET) i

Revision I Pa-e 9 of 16 CORE OPERATING LIMITS REPORT (COLR) ror BYRON UNIT I CYCLE 14 Heght Feet 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 MAX W(Z) 1.tXX)

I.INXXI 3.00(8 3.0(81 I.t0txx) l.O(X8) 1.28381 I.264t 1.2433 1.23.15 1.2192 1.2114 1.20.12

.1.127 I IS27 1.1709 1.1620 I.3387 I.1530 1.1477 1.1403 1.1 328 I.1352 1.1372 1.13RI 1.1378 1.1374 1.1443 1.1569 I.1676 1.1762 1.1877 1.1{914 I1J894 1.74 1.1803 I3.It )7 I Ihl2 I. 4'~)4 1.1974 1 1612 1.1754 3.2(350 1.2314 1.17503 l.OtXI()

I.exxx I.LOWXX I3.38883 338883N I3.tXXN)

Byron Unit 1 Cycle 14 Figure 2.6.2.c Summary of W(ZI Function at 14000 MWD/MTU (Top and Bottom 15%. Excluded per WCAP-10216) 1.35 1.30 1.25 z0 t1 FZ B.,

1.15 1.10

  • 1*

..I.

  • ILI

.1

.H..1.

-fbi.

{.:LV*4..

h I..

.1

1. O 0.00 2.00 4.00 6.00 8.00 10.00 12.00 CORE HEIGHT (FEET)

Revision I Page 10ol 16 CORE OPERATING L.IMITS REPORT (COL.R) for BYRON UNIT I CYCLE 14 Height Feet 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 560 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 940 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 MAX W(Z)

I.(X8X) 2 (XXII I.tXXX I.OHX) 1.2 t95 1.23)05 I.22ti9 1.2151 I.021(8 I. IS5S 1.1739 I.1660 1.1610 1.01560 I.1560 I1.1560 1.1641 I1.17h2

)1.1942 2.2262 1.2039 2.2067 1.2(X2 I.2073 1.222X 1.2.14 1.2431 I.24XS 1.2325 1.2642 1.r171 12.2742 1.22X) 1.21)0 I.24)12 I.IX48 2.2323 2.2542 I1.17X7 1.1747 I. 17(9 1.17.26 1.2121 I.2t47 I.27t8 I.2 4X) 2.270(1 I.2XX)

I ISHX)

I.IYHI)

I2.tPHX)

I.tPHXI

  • I.tPH10 Byron Unit 1 Cycle 14 Figure 2.6.2.d Summary of W(Z) Function at 20000 MWD/MTU (Top and Bottom 15% Excluded per WCAP-10216) 1.35 1.30 1.25 z0 C.)

Z 1.20 1.15 1.10 I.

.9.

1.05 nr:

onn u.uu 4.w L

i 4.00 6.00 8.00 10.00 12.00 CORE HEIGHT (FEET)

Revision I Page I I of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penal!y Factor (MWD/MTU)

F o(z) 667 1.0200 840 1.0215 1012 1.0256 11B4 1.0285 1357 1.0299 1529 1.0271 1702 1.0242 1874 1.0212 2047 1.0200 3253 1.0200 3598 1.0225 3771 1.0234 3943 1.0230 4288 1.0200 12391 1.0200 12563 1.0215 12736 1.0218 12908 1.0214 13081 1.0209 13598 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.

Revision I Pa-c 12o o16 CORE OPERATING LIMITS REPORT (C()LR) for BYRON UNIT I CYCLE 14 2.7 Nuclear Enthalpv Rise Hot Channel Factor (FNN1 (LCO 3.2.2) 2.7.1 FN < F"11.0 + PF(l.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FRTP 17 Fj =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 Channel Factor F NAH shall be calculated by the following formula:

UFAH = UFAHm where:

UF,,Hm, = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

F iH Warning Setpoint 2 2% of F N Margin FNAH Alarm Setpoint 2 0% of F NAH 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 Report, whichever is more conservative.

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

2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL 2 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER 2 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

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

Revision I Paste 13 or 16 CORE OPERATING LIMITS REPORT (COLR) For BYRON UNIT I CYCLE 14 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 120 -

100 -

I 0~

-3 wC a:

W 0

0 01~

80 60 40

(-1,,100) l+10,1100 Unac neptat le U

cce ptable

. Op ratio O

n A ceptable Operation er\\

, r I)

~.,

(-5, 50)(+25, 40) 20-0 -4 4

4 4 40 20 -10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

Revision I Pagc 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 2.10 Reactor Trip SVstem (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter 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 setpoint T..9coefficient K2 shall be equal to 0.0297 / "F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.001 81 /psi.

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 588.0 IF.

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

2.10.6 The measured reactor vessel AT lead/lag time constant '1 shall be equal to 8 sec.

2.10.7 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.

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

2.10.9 The measured reactor vessel average temperature lead/lag time constant X4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant T5shall be equal to 4 sec.

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

2.10.12 The fI (Al) 'positive" breakpoint shall be +10%/o Al.

2.10.13 The fI (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.

Revision I Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02/ 0F for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0/ 'F for decreasing Tavg.

2.11.4 The Overpower AT reactor trip selpoint Tavg heatup coefficient K6 shall be equal to 0.00245/ OF when T > T.

2.11.5 The Overpower AT reactor trip setpoint Ta.g heatup coefficient K6 shall be equal to 0/OFwhenTs 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 a, shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant X2 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 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant X6 shall be less than or equal to 2 sec.

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

Revision I Page 16 o' 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 2.12 Reactor Coolant System (RCS1 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 value given in the Table below (LCO 3.9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle.

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.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 values given in the Table below.

COLR Conditions Boron Concentration Section (ppm) 2.13.1 Refueling 1813 2.13.2 a) prior to initial criticality 1867 2.13.2 b) all other times in core life 2040

ATTACHMENT 2 Byron Station Unit 1 Cycle 14 Core Operating Limits Report Revision 2

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 14 (REVISION 2)

Revision 2 Page I oir 16 CORE OPERATING LIMITS REPORT (COLR) Ior BYRON UNIT I CYCLE 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cyclo 14 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 Salety 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,1)

LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBA)

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 (FRCS) Pressure, Temperature, and Flow Departlbre from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual alfecled 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 kelff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3. l.k Position Indication System - Shutdown (Special Test Exception)

Revisiott 2 Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented In the following subsections. Those limits are applicable for the entire cycle unless otherwise identified. Those limits have been developed using The NRC-approved methodologies specified in Technical Specilication 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 Thormal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.

6 60 6 60-225 60D 20 ia 0

0 2

co.

On Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

Revision 2 P;vgc 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON uNrr I CYCLE! 14 2.2 SHUTDOWN MARGIN (SOM)

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% uk/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 Coelficient (MTC) limits are:

2.3.1 The BOUARO/HIZP-MTC upper lrnit shall be +1.79 x 10okikA F.

2.32 The EOL/AROIHFP-MTC lower limit shall be -4.6 x 104 AWk kF.

2.3.3 The EOIJARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10' Ak/k/9F.

2.3.4 The EOLJARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 AWkk/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 Ltie HfFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limilts (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..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 lunction of park position:

l Park Posilion (step) l Overlap Limit (step) l 231 115

Rzevision 2 Page 4 of i6 224 220 200 180 E 160 E

to 140' CL CD8 TC 0

2100 to0

.X 80.

C 60-CORE OPERATING LIMITS REPORT (COLR) tor BYRON UNIT I CYCLE 14 Figure 2.5.1:

Control Bank Insertion Units Versus Percent Rated Thenmal Power (26 52%, 224)

(76.94 224)

BAN _B (100/%~ 161) 0 10 20 30 40 50 60 70 Relative Power (Percent) 80 90 100

Revision 2 i'age 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 2.G Heat Flux Hot Channel Factor &FQZ)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FQ(Z) S !QR-xK(Z) forP O.5 0.5 FRTP Fo(Z)

-S Q xK(Z) for P>0.5 P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER Fo P= 2.60 K(Z) is provided in Figura 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 Effective Full Power Days (EFPD). These values shall be used lo increase the FWo(z) as per Surveillance Requirement 32.1.2. 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 U'C@ =.,.U, where:

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

U, = Engineering uncertainty factor = 1.03 2.6.4 POMS Alarms:

Fo(Z) Warning Selpoint 2 2% of FO(Z) Margin Fo(Z) Alarm Setpolnt ' 0% of FO(Z) Margin

Revision 2 Page 6 of 16 CORE OPERATING LIMIIS REPORT (COI.R) for BYRON UNIT I CYCI.I 14 Figure 2.6.1 K(Z) - Normalized FO(Z) as a Function of Core Height 1.1 0

IL 0z 0

1 2

3 4

5 6

7 8

9 10 11 12 BOTTOM Core Height (ft)

TOP

Revision 2 Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 HeFgh Feet 0.00 020 0.40 0.60 0.80 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 320 340

.60 3.80 400 420 4.40 4.60 4B0 500 5.20 640 560

&90 6.00 6.20 6.40 660 6eo 7.00 7.20 7.40 760 7.80 8.00 -

8.20 a40 8.60 8a8 9.00 9.20 8.40 9.60 9so 10.00 1020 10.40 1060 10.80 1100 1120 11 40 1160 11.80 12.00 MAX W(Z)

I MMo 1.0080 I Ceirl 1101

$Pm 1.00M0 Ismn 1.1914 1.1970 I lilt.

1.1713 1.1540 1.1365 I.13'5 1.1334 1.1356 1.1353 1.1359 1.1402 1.1396 1.1379 1.1353 1.1324 1.1270 1.1271 1.1412

.16.29 L.T77 I '0

.1016 1.2117 1.2241 1.2:33 1.2329 1.242t I U46 1.2436 I.241w 1.2403 2.23*0 1244*

I2864 2.2509 1.299 1.2457 0.1390 I.0080 1.0000 I.MD I I00 l.OUO ID000C 1.0000 lWW0A I on Byron Unit I Cycle 14 Fkgure 2.6.2.a Sumray od W(Z) rucion *1150 MWDA4TU (Top and Botom 15% Excluded per WCAP-10216) 135 1.30 125 z0 9)

Z 1.20 1.15 1.10 1.05 L 0.00 L.-

1 1000o 1200 2.00 4.00 6.00 8.00 CORE HEIGHT IFEET)

Revision 2 IPayc 8 of 16 CORE OPERATING LIMITS RE-PORT (COLR) for BYRON UNIT I CYCLE 14 Heighl Feel 0.00 0.20 0.40 O.ZO 0.60 0.60 1.00 1.20 1.40

).60 1.90 2.00 2 20 2.40 2.60 2.80 100 0.20 3140 160 4.00 4 20 4.40 4.60 1.80 5.00 5.20 5.40 5.60 5.80

&00 6 20 640 6.60 5.80 7.00 7 20 7.40 7.60 7.b0 aL2 440 460 6.80 9.00 9.20 940 9.60 900 10.00 620 10.40 10.60 1060 11.00 11 20 11.40 I1.60 11.860 1200 MAX W(ZI l.Ocnn LOW 1.0000 1 000.

1.0000 1.0000 IAM~

1.0000 1.0000 1.1831 1.107 1.1537 1.131U 1.1339 1.1313 1.1235 1.1233 1.1213 3.3201 1.1191 1.1162 1.1133 1.1092 1.10D3 1.1013 1.0910 1.0t55 1.0922 1.0"s 1.112J 1.1324 1.1#75 1.2104 1.2113 12313 3.2402 J.2453 1.2503 1.2557 3.2623 1 270' 1.2t43 1.3003 1.3113 3 42.16 1.3348 1.3441 1.0000 1.00m 1.1) 1.0000 3.0001 I.mw l.OnJ 1.10000

.a1(oo Bron Unit I Cyde 14 Figae 2.2kb Surwary of W(Z) Fwsc3n al6000 oMWDA4TU (Top and Bano 35% E Ecdudod Pe WCAP.102 381 1.35 1.30 1.25 z0 F

Z 1.20 a!

1.15 1.10 3

I I I

- -I-

- 

-I.

7+

-I..-

t..

I

¶..

1

--

'.i.tfrifii

+/-7 iF.

-I_

1 1

I.

I 0o; l

0.00 2.00 4.1)0 6.00 CORE HEIGHT (FEE 8.00 10.00 12.00

_Y)

Rcvision 2 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) ror BYRON UNIT I CYCLE 14 Hslagt Feel 0.00 0.20 0.40 0.60 0.93 1.00 120 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 D.20 3.40 360 3.80 4.00 4.20 A 4n 4.60 460 5.00 S.20 5.40 5.60 5.80 6.00 6.20 6.40

&60 6.50 7.00 7.20 7.40 7.60 7.80

.8.00 8.20 a 40 61.60 8.80 9.00 9.20 940 960 980 10.00 1020 10.40 10.60 10.80 11.00 1220 11.40 11.60 11.80 12.00 MAX W(t) 1.0000 1.0w) ia0 1.2tn

,IXW 1 2721 1.2273 i2203 1.23W 1.283 1.1217 1.2m 1.2930 1.1135 111717 1.21J 1.1635 1.1585 1.1333 2.1372 1.1111 1.1371 1.1^7I 1.13 3 3.11703 1.1w" 1.1173 2.394!

1.1279 i.i333 1.131t 1.2306

..1740 1.2415 11.033 3.3429 3.1133 1.1130 1.1130 l-00w I.l<IG IDOCO Ivn BronUnh 1 Cycle 14 Fijve 2 6 2c Sufmvntyof W(Z) FWidioa.14000 MWUUTU lTop and 80tam 15% Exch6ed per WCAPO10216) t35 1.30 1.25 z0 E 1.20

.. 25 1.10 1.05 L..

0.00 2.00 4.00 6.00 8.00 CORE HEIGHT (FEET) 10.00 12.00 I

Rcvision 2 Page 10 of 16 COREr OPERATING UMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Heigt Feel 0.0U 0.20 0.40 060 0oo 1.00 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.e0 2.a0 3.00 3.20 3.40 3.80 3.8 4.00 4.20 4.40 4.60 4.80 5.00 5.20 640 5.60 5.80 t.00 6.20 040 4.60 6.80 7.00 7.20 7.40 7.60 7.90 8.00 0.20 8.40 8.60 8.80 900 920 9.40 9.60 9.80 10.00 1020 10.40 10.60 10 0 11.00 11.20 11,40 l1.60 11.80 12.00 MAX W(Z) 3.0000 3.0000 1.OOCO 3.0000 I 2cm 3230S l.orxln 1.253tx 1 2436 1.213*

1.2034 1.1902 1 2753 1.2393 1.1115 1.1370 1.1390 1.1390 1.1634 1.1741 I. IS4q 1.200 1.2D67 1.2063 I.210' L.2313 1.249 2 2543 12M 1.260 1.2513 I 2374 1.22I7 1.2112 1.1"D

.I1'M

.IM3t 1.1712 1.1733 1.1713 1 2972 1.2364 3.27n2 I3079 3.0000 1.11)(1 1.0000 1.0000 1.0000 1.0000 1.0000 2.n0oo Byron Uni I Cycle 14 Fowe 2.6 2 d Sunmmay of W(2) Fuction a2 2000D MWDIMTU (Top and Bottom 15% Excluded pef WCAP1 02 16) 1.35 1.30 1.25 2

z 0.20 1.1 1.20 Hf H+/-I 10.00 12.00 1 1.05 I 0.00 2.00 4.00 6.00 8.00 CORE HEIGHT (FEET)

Revisiun -1 Page I Iof 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalt Factor (MWDIMTU)

Zo(z) 495 1.0200 667 1.0240 840 1.0280 1012 1.0306 1185 1.0316 1529 1.0302 1702 1.0268 1874 1.0241 2047 1.0221 2219 1.0209 2564 1.0206 2736 1.0213 2909 1.0222 3081 1.0233 3254 1.0241 3426 1.0245 3599 1.0243 3771.

1.0234 3943 1.0216 4116 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.

0.

RC'V;S;On 2 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) tOr BYRON UNIT I CYCLE 14 2.7 Nuclear Enthalry Rise J101 Channel Factor (FN (LCO 3.2.2) 2.7.1 FNAH S Fl(1.0 + PFhH,(.0 P)l where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F.R4M= 1.70 PFe, 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty. Ur,3", to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN 4 shall be calculated by the following formula:

U FMH = UFA where:

Us X = Base FNAH measurement uncertainty 1.04 2.7.3 PDMS Alarms:

F"m Warning Setpoint 2 2% of F'~ Margin FNH Alarm Setpolnt 2 0% of FNM Margin 2.8 AXIAL FLUX DIFFERENCE (AFDi (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limils 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 NucleateBoilinn Ratio (DNBF1) (LCO 3.2.5) 2.9.1 DNBRAPst Ž 1.536 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 Setpointl 22% of DNBR Margin DNBR Alarm Selpoint 2 0%/a of DNBR Margin

Revision 2 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 0~

a:

-J D

I-:

0 I

4 0i 120~

100 -

Unac epta le 80 Op ratio.

60 -

40

.(7

.1 20 0

I 40 20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

I II

Revision 2 Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) flir BYRON UNIT I CYCLE 14 2.10 Reactor Trio Svstem (RTS) Instrumentation (LCO 3.3.1) - Overtempetature AT Setpoint Parameter 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 setpoint T, vcoefficient 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 to 588.0 "F.

2.10.5 The nominal RCS operating pressure (indicated) Pi shall be equal lo 2235 psig.

2.10.6 The measured reactor vessel AT lead/lag time constant Tr 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 r3 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant r4 shall be equal to 33 sec.

2.10.1 0 The measured reactor vessel average temperature lead/lag time constantk shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant -r6 shall be less than or equal 1o 2 sec.

2.10.12 The f1 (Al) 'positive breakpoint shall be +1 0M. Al.

2.10.13 The f, (Al) 'negative" breakpoint shall be -1 8% Al.

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

2.10.15 The f (Al) "negative' slope shall be -2.61% l% Al.

Revision 2 Page 15 of 16 CORE OPERATING LIMITS RE-PORT (COLR) for BYRON UNIT I CYCLE 14 2.11 Reactor Trip SVstem (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Solpoint 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 KS shall be equal to 0.02 / 'F for increasing T a 2.11.3 The Overpower AT reactor trip setpoint T,,0 rate/lag coefficient Ks shall be equal to 01/ F for decreasing T.

2.11.4 The Overpower AT reactor trip selpoint T,,, heatup coefficient 1K shall be equal to 0.00245 / IF when T > T'.

2.11.5 The Overpower AT reactor trip selpoint T as heatup coefliclent K6 shal be equal to 0 'IF when Ts< T.

2.11.6 The nominal T. at RTP (indicated) To shall be less than or equal to 588.0 'F 2.11.7 The measured reactor vessel AT lead/lag time constant Tc shafl be equal to 8 sec.

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

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

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

2.11.11 The measured reactor vessel average temperature rate/lag time constant X7 shall be equal to 10 sec.

2.11.12 The 12 (AQ) positiveW breakpoint shall be 0 for all I.

2.11.13 The 12 (AI) 'negative' breakpoint shall be 0 for all Al.

2.11.14 The 12 (Al) 'positive' slope shall be 0 for all Al.

2.11.15 The f2 (A) "negatives slope shalN be 0 for all Al.

Revision 2 Page 16 or 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 14 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 prossure shall be greater than or equal to 2209 psig.

2.12.2 The RCS average temperature (T.,c) shall be less than or equal 1O 593.1 IF.

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 value given in the Table below (LCO 3.9.1). The reported 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. or 5 (TRM TWCO 3.1.g Required Action B2 and TRM TWCO 3.1.k.2), the Reactor Coolant System boron concerdration shall be greater than or equal to the values given In the Table below.

COLR Conditions Boron Concentration Section (ppm) 2.13.1 Refueling 1813 2.13.2 a) prior to initial criticality 1867

.i 2.13.2 b) all other times in core life 2D40I

Retrieved from "https://kanterella.com/w/index.php?title=BYRON_2005-0037,_Cycle_14_Core_Operating_Limits_Report&oldid=5385879"