BYRON 2003-0093, Issuance of Core Operating Limits Report for Byron Unit One Cycle 13

Issuance of Core Operating Limits Report for Byron Unit One Cycle 13

ML032880451
Person / Time
Site:	Byron
Issue date:	10/07/2003
From:	Kuczynski S Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.01.0700, BYRON 2003-0093
Download: ML032880451 (20)

Text

Exelen.

Exelon Generation Company, LLC www.exeloncorp.com Nuclear Byron Station 4450 North German Church Road Byron, IL 61010-9794 October 7, 2003 LTR: BYRON 2003-0093 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit I Facility Operating License No. NPF-37 NRC Docket No. STN 50-454

Subject:

Issuance of Core Operating Limits Report for Byron Station Unit One Cycle 13

References:

(1) Licensee Event Report 454-2003-003-00, 0Licensed Maximum Power Level Exceeded Due to Inaccuracies in Feedwater Ultrasonic Flow Measurements Caused by Signal Noise Contaminations Dated September 29, 2003 (2) Letter from Mahesh Chawla (NRC) to John L. Skolds (Exelon Generation Company, LLC), "Byron Station Unit 1 and 2, Exemption from the Requirements of 10 CFR 50.44, 10 CFR 50.46, and 10 CFR Part 50 Appendix K," Dated September 22, 2003 In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the COLR for Byron Station, Unit 1 Cycle 13.

One reload parameter pertains to the Byron Station Unit I Best Estimate Large Break Loss of Coolant (BELOCA) Accident composite Peak Clad Temperature (PCT). The BELOCA analyses,.

operating envelope was expanded for Cycle 13 and resulted in an increase of 800F above the base evaluation. The resultant PCT of 21360 F continues to satisfy the 10CFR 50.46 requirement of less than 22000F. The reporting requirements of 10CFR50.46 will be satisfied in a separate letter within 30 days following the start of the cycle.

The nuclear design and safety analyses also considered the possible cumulative effects from overpower operation of Byron Station Units 1 and 2 that may have occurred due to the recently identified inaccuracies in the Ultrasonic Flow Measurement System flow correction factors. (See reference 1)

Cycle 13 will include four Lead Test Assemblies (LTA) that contain features requiring NRC approval. The LTAs will contain 24 new fuel rods that contain a low- low tin (LT-2) alloy of ZIRLO.

In reference 2, the NRC has granted a temporary exemption from the requirements of 10CFR 50.44, 10CFR 50.46, and 10CFR Part 50, Appendix K, for the LTA assembly containing the 24 ZIRLO LT-2 fuel rods. The second feature is the high bumup evaluation of the LTAs. The four assemblies are expected to exceed the license limit burnup of 60,000 MWD/MTU. During the reload design and safety analyses, the use of four high bumup LTAs was evaluated and found acceptable. A License Amendment Request will be submitted to obtain NRC approval to exceed AUDI

0 the design basis rod average burnup limit (60,000 MWD/MTU) for the LTAs prior to exceeding the 60,000 MWDIMTU rod average burnup limit.

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

Respectfully,

,5 X.

Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station

Attachment:

Byron Station, Unit I Cycle 13, COLR 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

Attachment Byron Station, Unit I Cycle 13, COLR

FRTHD-03-99 CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 13

F:RTHD-03-99 Page'I of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 13 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 31.5 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 (F0 (Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F",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)

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 21.0 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)

FRETHD-03-99 Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 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 (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.

j 680 2471 psia 660 2250 psia as Q>

W 640 01 W

C, E

a>

0) 620 6D 00 SUU 580

. .o 4 2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

FRTH3D-03-99 Paje 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 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 limits for MODE 5 are:

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 3.1.1 and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOUARO/HZP-MTC upper limit shall be +1.93 x 1i6 Ak/kPF.

2.3.2 The EOUAROIHFP-MTC lower limit shall be -4.6 x 104o Akk/F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Akk/F.

2.3.4 The EOUARO1HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 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 Ufe HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Umits (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) l 228 l 113 l

FRlTHD-03-99 Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Figure 2.5.1:

Control Bank Insertion Umits Versus Percent Rated Therma Power 224 (27%, 224) (77%, 224) 220 l

200 180 3 160 (100°/^ 161)

E

§ 140 C.

t 120 C

0

=In 100 0

a8 460 40) 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

FRTHD-03 99 Paoe 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 2.6 Heat Flux Hot Channel Factor (Fg)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FR1T FQ(Z) C xK(Z) forP<0.5 0.5 FRT FQ(Z) < *Q xK(Z) forP>0.5 P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FR = 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 bumups of 150, 6000,

'14000, and 20000 JWD/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 Iwo(z) as per Surveillance Requirement 3.2.1.2. A 2%penalty factor shall be used at all cycle bumups that are outside the range Of Table 2.6.2.

2.6.3 Uncertainty

The yncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula UFQ =UI a U.

where:

Uw = Base FO measurement uncertainty = 1.05 when PDMS is Inoperable (Uqu is defined by PDMS when operable.)

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

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

FRTHD-03-99 Page 6of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Figure 2.6.1 K(Z) -- Normalized F0 (Z) as a Function of Core Height 1.1 1

0.9 0.8 0.7 0.6 0

w 0.5 8:

0.4 0.3 0.2 0.1 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP

FRTHD-03-99 Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Height MAX W(Z)

Feet Byron Unit I Cycle 13 0.00 1.0000 0.20 Figure 2.6.2.a 0.40 1.0000 l.OOCO Summ ary ol W(Z) Function a1150 MW DIMTU 0.60 LOOCO 0.80 l.uOX (Top and Bottom 15% Excluded per WCAP-10216) 1.00 l.OXOD 1.20 1.0000

.acoo 0 1.40 1.60 1.0758 3.80 2.00 2.20 2.40 1469 2.60 1.2295 2.80 1.2119 3.00 1.1954 3.20 1.1782 1.30 3.40 1.1705 3.60 1.1659 3.80 1.1614 4.00 1.1563 4.20 1.1497 4.40 1.1437 4.60 1.1351 4.80 1.1275 1.25 5.00 1.1231 5.20 1.1226 5.40 5.60 5.80 1.12112 1.1186 1.1168 z

I rL 6.00 1.1135 6.20 6.40 1.1095 1.1212 = 1.20 6.60 13.330 6.80 1.1427 7.00 1.1515 7.20 1.15S4 7.40 1.1642 7.60 1.1694 7.80 1.1750 1.15 8.00 1.1783 6.20 1.1824 8.40 1.1869 5.60 6.60 1.1889 1.1909 VI 9.00 1.1938 9.20 1.1963 9.40 1.1981 1.10 9.60 1.1932 9.80 1.1949 10.00 1.1975 10.20 1.1940 10.40 1.0000 10.60 10.80 1A0 11.00 1. 05 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 WXD 11.40 11.60 1.0000 CORE HEIGHT (FEET) 11.80 _ . _

12.00 1.0000

FRTHD-03-99 , . Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Height MAX W(Z)

Feet Byron Unit 1 Cycle 13 0.00 3.0000 Figure 2.6.2.b 0.20 0.40 3.0000 0.60 Summary ot W(Z) Function al 6000 MWDIMTU 1.0000 0.80 ITop and Bottom 15% Excluded per WCAP110216) 1.00 1.0000 1.20 1.40 1.0000 11.0000 1.60 1.35 1.80 1.3077 2.00 1.2SS2 2.20 1.2651 2.40 1.2426 2.60 1.2120 2.80 1.1960 3.00 1.186 3.20 1.1832 1.30 3.40 1.1777 3.60 1.1703 3.80 4.00 3.1565 4.20 1.1466 4.40 1.1332 4.60 1.1267 1.25 __ _____4_ __ __ J4 4.80 1.1163 5.00 1.1059 5.20 1.I031 . __________._______

5.40 11.1060 5.60 1.3115 5.80 1.1161 6.00 1.1196 6.20 = 1.20 6.40 1.1232 1.1246 6.60 6.80 1.108D 1.1266 IL H.

I~~~~~

7.00 1.1344 7.20 1.1318 7.40 1.1489 7.60 ".l549 7.80 1.1643 1.15 8.00 1.12667 8.20 1.1911 1.2344 8.40 I.2043 1.141S 1.2161 8.60 1.1492 1.2330 3.60 9.00 1.2498 9.20 9.40 1.177S 1.164S 1.10 9.60 9.80 1.1911 1J000 10.00 1im 1.2162 10.20 1.1330 10.40 1.249S 1.2S0l 10.60 1.1=0 10.80 1.2=6 11.00 1 (5 1 0000 11.20 0.00 2.00 4.00 6.00 8.00 10.00 120oo 1 0000 11.40 CORE HEIGHT (FEET) 11.60 11.80 12.00 1.0000

FRTHD-03-99 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 13 Height MAX IN(Z)

Feet Byron Unit 1 Cycle 13 0.00 1.0000 0.20 1.0000 Figure 2.6.2.c 0.40 1.000 0.60 1.0000 Summary of W(Z) Function at 14000 MWDIMTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.A00 1.20 1.0000 1.4p 1.0000 1.60 1.0000 1.35 1.60 1.2516 I 2.00 1.2438 220 1.2326 2.40 L.2233 2.60 1.2109 2.80 3.00 1.1887 3.20 1.1782 1.30 1.1732 4 3.40 3.60 1.1691 3.80 1.1646 4.00 1.1595 4.20 1.1538 4.40 1.1464 4.60 1.1426 4.80 1.1449 1.25 5.00 1.1454 5.20 1.1448 4 5.40 1.1444 5.60 1.1531 z 6.60 1.166 6.00 1.1773 6.20 1.1869 z 1.20 - - . .4 ...4 6.40 1.1936 6.60 1.1983 6.50 1.2DII 4 7.00 4 1.2021 7.20 1.2007 4 7.40 4 7.60 1.1953 4 7.60 1.1883 1.15 8.00 1.1835 8.20 1.1762 8.40 1.1691 8.60 1.1598 B.80 1.1634 9.00 1.173 9.20 1.1833 9.40 1.192D 1.10 9.60 1.1998 9.80 1.230D 10.00 1.263D 10.20 1-240 10.40 1.0000 10.60 1.0000 10.80 11.00 i os 1.000 11.20 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.00M CORE HEIGHT (FEET) 11.60 11.80 IAIXUD 12.00

FRTHD-03-99 Page 10 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Height MAX W (Z)

Feet Byron Unit 1 Cycle 13 0.00 1.UXD 0.20 1.00W Figure 2.6.2.d 0.40 1.00W 0.60 1.0000 Summary of W(Z) Function at 20000 MW DOIMTU 0.80 1.0000 (Top and Bottom 15% Excluded perWCAP-10216) 1.00 1.00 1.20 I.00W 1.40 1.0OO 1.60 1.0000 ' 1.40 1.80 1.2761 2.00 1.2577 2.20 1.2357 2.40 1.2236 2.60 1.2095 2.80 1.1967 3.00 1.1839 1.35 3.20 1.1765 3.40 1.1807 3.60 1.1831 3.80 1.1855 4.00 1.170 4.20 1.1931 4.40 1.2027 1.30 4.60 1.2090 4.30 1.2143 5.00 1.2176 5.20 1.2185 5.40 1.2222 5.60 1.2386 125 5.80 1.2539 6.00 1.2655 6.20 I.Z732 6.40 1.27S8 6.60 1.2786 6.80 7.00 1.27W3 1.2771 1.20 iri 7.20 1.2712 7.40 1.2641 7.60 1.2526 7.80 1.2404 8.00 1.2270 8.20 1.26 1.15 8.40 1.1924 8.60 1.1815 8.80 1.1238 9.00 1.1827 9.20 1.1822 9.40 1.1980 9.60 1.2510 1.10 9.80 1.24D 20.00 1.3320 10.20 1.3690 10.40 l.000 10.60 1.0OOD 10.30 11.00 I.000 1.0000 1.05 --- FFTT 11.20 I.000 0.00 2o0 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.30 1.00o 12.00 I.000D

FRTHD-03-99 Page II of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor - F>o(z)

(MWD/MTU) (%)

.. 1697 2.00 1869 2.05 2041 2.06 2213 2.00 14245 2.00 14417 2.01 14589 2.29 14761 2.21 14932 2.13 15104 2.05 15276 2.00 Notes: IL Unear interpolation is adequate for intermediate cycle bumups.

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

FRlTHI)-03-99 Paoe 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 2.7 Nuclear Enthalov Rise Hot Channel Factor (F"AHI (LCO 3.2.2) 2.7.1 FN^ = F A[1 .0 + PFm(11.0 - P)J where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F = 1.70 PFm - 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FaiN shall be calculated by the following formula:.

UFAH = UFai n where:

UFH. = Base FN&H measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNAH Warning Setpolnt 2 2% of FNAH Margin FNAH Alarm Setpoint 2 0% of F"AH Margin 2.8 Axial Flux Difference (AFD) (LC0 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 Acceptable Operation Limits are applicable.

2.9 Denarture from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL 2 1.536 The Axial Power Shape Limiting DNBR (DNBRjpsL) is applicable with THERMAL POWER

> 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

FRTHD-03-99 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits w Ith PDMS Inoperable 120 100 ir 0

9-60 w

VI a:

0 I.-

40 20 0

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

FRTHD-03-99 Page 14 of I16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 2.10 Reactor TOP System (RTS) Instrumentation (LCO 3.3.1) - Overte~mperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpolnt K, shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint T., coefficient K2 shall be equal to 0.0297 1F .

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

2.10.4 The nominal T. at RTP (indicated) r shall be Jess 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 tr, shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel AT lag time constant T3shall 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 i5 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 to 2 sec.

2.10.12 The 11(Al) "positivet breakpoint shall be +10% AI. '

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

2.10.14 The f1, (A) 'positivei slope shall be +3.47% I% Al.

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

RTHD)03-99 Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 2.11 Reactor Trip System ARTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint T., rate/lag coefficient K5 shall be equal to 0.02 I OF for increasing T ,

2.11.3 The Overpower AT reactor trip setpoint T., ratellag coefficient Ks shall be equal to 01 OF for decreasing T,.

2.11.4 The Overpower AT reactor trip setpoint T,, heatup coefficient K5 shall be equal to 0.00245 / OF when T > T'.

2.11.5 The Overpower AT reactor trip setpoint T. heatup coefficient Ke shall be equal to 0/

'F when T

• 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 Is shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant r2 shall be equal to 3 sec.

2.11 9 The measured reactor vessel AT lag time constant S shall be less than or equal to 2 sec.

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

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

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

2.11.13 The f2 (Al) negativem 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

FRTHD-03-99 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 13 2.12 Reactor Coolant System (RCS) Pressure. Tempnerature, and Flow DeDarture 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 (Te) 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 1812 ppm (LCO 3.9.1).

2.13.2 To maintain keff < 0.987 with all shutdown and control rods fully withdrawn In MODES 3, 4, or 5 (TRM 3.1.g Required Action B.2 and TRM TWCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to:

a. 1836 ppm prior to initial criticality.

b. 1999 ppm at all other times In core life.