BYRON 2002-0005, Revision 1 to Byron Stations 1 and 2, Cycles 11a and 10a, Core Operating Limits Reports

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Revision 1 to Byron Stations 1 and 2, Cycles 11a and 10a, Core Operating Limits Reports
ML020390337
Person / Time
Site: Byron  Constellation icon.png
Issue date: 01/17/2002
From: Lopriore R
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
-nr, BYRON 2002-0005
Download: ML020390337 (34)
v • d • e


Text

Exelon..

Exelon Generation Company, LLC wwwexeloncorp.com N uc e ar Byron Station 4450 North German Church Road Byron, IL61010-9794 January 17, 2002 LTR: BYRON 2002-0005 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

Revision 1 to Byron Station, Unit 1 Cycle 1 1A, Core Operating Limits Report and Revision 1 to Byron Station, Unit 2 Cycle 10A, Core Operating Limits Report

Reference:

Letter from R. L. Lopriore (Exelon Generating Company, LLC) to the NRC, "Byron Station, Unit 1 Cycle 1 1A, Core Operating Limits Report and Byron Station, Unit 2 Cycle 10A, Core Operating Limits Report," dated May 22, 2001 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 1 1A, and Byron Station, Unit 2 Cycle 1 OA. The Unit 1 and Unit 2 COLRs were revised to add an End of Life, All Rods Out, Hot Full Power Moderator Temperature Coefficient limit at 60 parts per million Reactor Coolant boron concentration and to consolidate the shutdown margin limits for the various modes. In addition for Unit 2, the Hot Full Power, Axial Flux Difference upper limit was revised from +5% to +10% with the Power Distribution Monitoring System inoperable.

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

Respectfully, Site Vice President Byron Nuclear Generating Station Attachments: 1) Byron Station, Unit 1 Cycle I1A, COLR, Revision I

2) Byron Station, Unit 2 Cycle 10A, COLR, Revision I RPL/JLdpk 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 1 Byron Station Unit I Cycle 11A Core Operating Limits Report Revision I

NUCLEAR FUEL MANAGEMENT DEPARTMENT TRANSMITTAL OF DESIGN INFORMATION 0 SAFETY RELATED Originating Organization NFM ID # NFM0100048 LI NON-SAFETY RELATED Z Nuclear Fuel Management Rev. No. I C REGULATORY RELATED E] Other (specify) Page I of 15 Station Byron Unit I Cycle IIA Generic To: Kenneth N. Kovar- Byron Subject Byron Unit I Cycle I IA Core Operating Limits Report in ITS Format and W(z) Function Brian L. Manges /3t/7-0 -- / /1i ,/tA ,267  ?*A)/

Preparer lreparer's Signature " Date Tyrone L. Stevens hwI/00 Cf Reviewer Review r Signatur Date D. Redden ,Z NFM Supervisor Approver's Signature Date Status of Information: 0 Verified M Unverified El Engineering Judgement Method and Schedule of Verification for Unverified TODIs:

Description of Information:

Attached is the Byron Unit I Cycle II A Core Operating Limits Report (COLR) in the ITS format and W(z) function. This COLR is for uprate at 3586.6 MWt. Revision 1 of this TOD] supercedes Revision 0.

Purpose of Information:

In Revision 1, the SDM limits for MODE 5 were revised to 1.3% Ak/k for LCO 3.1.1. Revision I also incorporates the EOL HFP ARO MTC surveillance limit at 60 ppm. Byron Station is requested to perform a Plant Review of this document. Upon completion of the Plant Review, Byron Station is to transmit the COLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 5.6.5. Please provide NFM (Brian Manges) with a copy of Byron Station's completed Plant Review and COLR submittal to the NRC.

Source of Information:

I. Westinghouse Letter 01CB-G-057 (CAC-01-104), dated April 6, 2001

2. TODI NFM00001 88, Sequence 0 "Pressurizer Pressure DNB Limit", A. W. Wong to D. Wozniak and T. Luke, December 15, 2000
3. Westinghouse Letter 01CB-G-047 (ASD-01-90), dated March 23, 2001
4. Westinghouse Letter CAC-0I-123, dated April 11, 2001
5. TODI NFM0100054, Sequence 0, "RCS Average Temperature DNB Limit", A. Wong to D. Wozniak and C. Dunn, dated 4/19/2001 Supplemental Distribution: P. E. Reister / J. E. Langan (BY)

TODI NFMO100048 Rev. I Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I I A 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 11A 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 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 (FNAH)

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) DNB Parameters 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)

TODI NFMO100048 Rev. 1 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA 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 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.

680 2471 psia 660 _ _-I 2250 psia Cn3 640 4 .-

0)

E 0 psia, S-1..

600 5a) , t , , I * ,

580

.4 .6 .8 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

TODI NFM0100048 Rev. I Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA 2.2 Shutdown Margin (SDM)

The SDM limit for MODES 1, 2, 3, 4, and 5 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, 3.1.i, and 3.1.j).

2.3 Moderator Temperature Coefficient (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +3.73 x 10.5 Ak/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10 4 Ak/k/°F.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be less negative than or equal to -3.7 x 10' Ak/k/IF.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be less negative than or equal to -4.3 x 1 0 4 Ak/k/°F where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limit (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 a 113 step overlap limit.

TODI NFM0100048 Rev. I Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 200 180 (100%, 161) 160 CL 140 1.

120 0.

100 0,

CO 0

0: 80 60 40 20 0

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

TODI NFMO100048 Rev. I Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA 2.6 Heat Flux Hot Channel Factor (F 0 (Z) (LCO 3.2.1) 2.6.1 F RTP FQ(Z) <- xK(Z) forP <0.5 0.5 F RTP FQ (Z) <' xK(Z) for P > 0.5 P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER RTP FT = 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.c The normal operation W(Z) values have been determined at burnups of 8801, 14000, and 18000 MWD/MTU.

For this cycle, the Fco(z) penalty factors are equal to 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FwQ(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups.

Multiplication Factor = 1.02

2.6.3 Uncertainty

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

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is Inoperable Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

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

TODI NFMO100048 Rev. I Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA Figure 2.6.1 K(Z) - Normalized FG(Z) as a Function of Core Height 1.1 (0.0 1.0) (6.0,1.0) f-oft(12.(

law-ft

,0.924) 0.9 0.8 N0.7 U

4 0.6 E

0 0.5 z

N e 0.4 -. ,--LOCA Limiting Envelope 0.3 0.2 0.1 0

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

TODI NFM0100048 Rev. I Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA Height MAX W(Z)

Feet Byron Unit I Cycle I IA 0.00 1.0000 0.20 1.0000 Figure 2.6.2.a 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 8801 MWDIMTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP- 10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.40 1.80 1.1812 2.00 1.1675 2.20 1.1513 2.40 1.1408 2.60 1.1293 2.80 1.1198 3.00 1.1104 3.20 1.1040 1.35 3.40 1.1010 3.60 1.1046 3.80 1.1102 4.00 1.1155 4.20 1.1206 4.40 1.1247 4.60 1.1285 4.80 1.1306 1.30 5.00 1.1324 5.20 1.1323 5.40 1.1311

__-AP 5.60 1.1288 5.80 1.1375 z 0

6.00 1.1490 C,,

6.20 1.1596

1.25 6.40 1.1682 U

6.60 1.1748 6.80 1.1804 7.00 1.1940 7.20 1.2082 --

7.40 1.2212 7.60 1.2315 7.80 1.2410 1.20 8.00 1.2519 8.20 1.2619 8.40 1.2721 8.60 1.2811 8.80 1.2904 9.00 1.2989 9.20 1.3087 9.40 1.3185 1.15 9.60 1.3264 9.80 1.3344

-- ~ -4 10.00 1.3461 -4 -

10.20 1.3678 10-40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.10 11.20 1.0000 0.010 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFM0100048 Rev. I Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 1IA Height MAX W(Z)

Feet Byron Unit I Cycle I IA 0.00 1.0000 0.20 1.0000 Figure 2.6.2.b 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 14000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.40 1.80 1.2398 2.00 1.2294 2.20 1.2169 2.40 1.2055 2.60 1.1907 2.80 1.1766 3.00 1.1622 3.20 1.1590 3.40 1.1600 1.35 3.60 1.1620 3.80 1.1620 4.00 1.1632 4.20 1.1678 4.40 1.1747 4.60 1.1814 4.80 1.1862 5.00 1.1889 5.20 1.1904 5.40 1.1898 1.30 5.60 1.2058 z

5.80 1.2203 4 4 6.00 1.2328 I-6.20 1.2434 z 6.40 1.2500 U-6.60 1.2517 4 6.80 1.2534 7.00 1.2537 7.20 1.2508 1.25 7.40 1.2469 7.60 1.2401 7.80 1.2332 8.00 1.2243 8.20 1.2115 8.40 1.1996 8.60 1.1853 8.80 1.1769 9.00 1.1842 1.20 9.20 1.1935 9.40 1.2341 9.60 1.2747 9.80 1.3093 4  :

10.00 1.3409 10.20 1.3686 4g~*

10.40 1.0000 10.60 1.0000 10.80 1.0000 I1.00 1.0000 1.15 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFM0100048 Rev. I Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 11 A Height MAX W(Z)

Feet Byron Unit I Cycle I IA 0.00 1.0000 0.20 1.0000 Figure 2.6.2.c 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 18000 MWD/MTU 0.80 I.0000 (Top and Bottom 15% Excluded per WCAP- 10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.45 1.80 1.2333 2.00 1.2230 2.20 1.2102 2.40 1.1972 2.60 1.1819 2.80 1.1669 3.00 1.1526 1.40 3.20 1.1450 3.40 1.1511 3.60 1.1554 3.80 1.1597 4.00 1.1656 4.20 1.1782 1.35 4.40 1.1890 4.60 1.1975 4.80 1.2041 5.00 1.2086 5.20 1.2108 5.40 1.2122 5.60 1.2284 1.30 z

5-80 1.2449 6.00 1.2585 0 6.20 1.2681 C,)

z 6.40 1.2757 U.

6.60 1.2774 6.80 1.2782 7.00 1.2768 1.25 7.20 1.2733 7.40 1.2679 7.60 1.2571 7.80 1.2469 8.00 1.2337 8.20 1.2186 1.20 8.40 1.2047 8.60 1.1922 8.80 1.1965 9.00 1.2001 9.20 1.2363 9.40 1.2828 9.60 1.3274 1.15 9.80 1.3669 10.00 1.4026 10.20 1.4333 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.10 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 I140 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFMO100048 Rev. I Page I Iof 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE IA 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2)

N RTP 2.7.1 FAH < FAH [1.0 + PFH(1O.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER RTP FAH = 1.70 PFAH = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FAHNN shall be calculated by the following formula:

UFAH = UFAHm where:

UFAHn = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNAH Warning Setpoint _> 2% of FN AH Margin FN6H Alarm Setpoint 2! 0% of FN AH 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 Acceptable Operation Limits are applicable.

2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL ->1.659 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER

Ž 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

TODI NFM0100048 Rev. I Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 11 A Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Aal RHuK ffbBce Uirlts 12J 0~

A0-30-23-1O 0 10 23 30M40 5 ppFLU- 0( 0

TODI NFMO100048 Rev. I Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT ICYCLE 1IA 2.10 Reactor Trip System Overtemperature AT Setpoint Parameter Values (LCO 3.3.1) 2.10.1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.

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

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

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

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

2.10.6 The measured reactor vessel AT lead/lag time constant -T1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel AT lag time constant 3shall 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 constantt"5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant T6 shall be less than or equal to 2 sec.

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

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

TODI NFMO100048 Rev. I Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT ICYCLE 11A 2.11 Reactor Trip System Overpower AT Setpoint Parameter Values (LCO 3.3.1) 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 / OF for increasing Tavg.

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

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

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / 'F when T < T".

2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 OF.

2.11.7 The measured reactor vessel AT lead/lag time constant t1 shall be equal to 8 sec.

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

2.11.9 The measured reactor vessel AT lag time constant c3 shall 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 t7 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.

TODI NFM0 100048 Rev. I Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 11 A 2.12 Reactor Coolant System (RCS) DNB Parameter 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 IF.

2.12.3 The RCS total flow rate shall be greater than or equal to 380,900 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 2000 ppm (LCO 3.9.1).

2.13.2 The Reactor Coolant System boron concentration shall be greater than or equal to 2075 ppm at all 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 (TLCO 3.1.g and TLCO 3.1.k)

ATTACHMENT 2 Byron Station Unit 2 Cycle 10A Core Operating Limits Report Revision I

NUCLEAR FUEL MANAGEMENT DEPARTMENT TRANSMITTAL OF DESIGN INFORMATION 0 SAFETY RELATED Originating Organization NFM ID # NFM0100050 El NON-SAFETY RELATED [D Nuclear Fuel Management Rev. No. I El REGULATORY RELATED El Other (specify) Page 1 of 16 Station -Byron Unit 2 Cycle 10A Generic To: Kenneth N. Kovar - Byron Subject Byron Unit 2 Cycle 1OA Core Operating Limits Report in ITS Format and W(z) Function Brian L. Manges __ _ _ _ __ _ _ _ i 7 Preparer Prep er's Signature ¢ Date Tyrone L.Stevens - 2.Jlh~

Reviewer Revi9der's Signature Date D.Redden k _/o/~

NFM Supervisor Approver's Signature Date Status of Information: Verified El Unverified El Engineering Judgement Method and Schedule of Verification for Unverified TODIs:

Description of Information:

Attached is the Byron Unit 2 Cycle IOA Core Operating Limits Report (COLR) in the ITS format and W(z) function. This COLR is for uprate at 3586.6 MWt. Revision I of this TODI supercedes Revision 0.

Purpose of Information:

In Revision 1, the SDM limits for MODE 5 were revised to 1.3% Ak/k for LCO 3.1.1. Revision I also incorporates the EOL HFP ARO MTC surveillance limit at 60 ppm. Finally Revision I revises the AFD band to +10 at HFP conditions (Figure 2.8. 1). Byron Station is requested to perform a Plant Review of this document. Upon completion of the Plant Review, Byron Station is to transmit the COLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 5.6.5.

Please provide NFM (Brian Manges) with a copy of Byron Station's completed Plant Review and COLR submittal to the NRC.

This TODI supercedes Reference 7.

Source of Information:

I. Westinghouse Letter 01 CB-G-194 (CAC-01-289), dated December 6, 2001

2. TODI NFMO000 188, Sequence 0 "Pressurizer Pressure DNB Limit", A. W. Wong to D. Wozniak and T. Luke, December 15, 2000
3. Westinghouse Letter 01CB-G-076 (ASD-01 -113, Rev 1), dated April 16, 2001
4. TODI NFM0100054, Sequence 0, "RCS Average Temperature DNB Limit"; A. W. Wong to D. Wozniak and C. Dunn, dated April 19, 2001
5. TODI NFM0100040, Revision 0, "Byron Unit 2 Cycle IOA OTAT and OTAP Setpoint Values", dated March 30, 2001
6. Westinghouse Letter 01CB-G-196 (ASD-01-276), dated December 5, 2001 Supplemental Distribution: P. E. Reister / J. E. Langan (BY)

TODI NFM0100050 Rev. I Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 10A 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 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 (F NAH)

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) DNB Parameters 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)

TODI NFMO100050 Rev. I Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 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 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.

680 2471 psia 660 LL_ 2250 psia 1a) 640 L~.

0l)

E I-620 a) 600 580 0 -2 .4 .6 .8 1 1 2 Fraction of Nominol Power Figure 2.1.11: Reactor Core Limits

TODI NFMO100050 Rev. I Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 2.2 Shutdown Margin (SDM)

The SDM limit for MODES 1, 2, 3, 4, and 5 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, 3.1.i, and 3.1.j).

2.3 Moderator Temperature Coefficient (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.0 x 105 Ak/k/°F.

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

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be less negative than or equal to -3.7 x 10' Ak/k/°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be less negative than or equal to -4.3 x 10-4 Ak/k/°F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limit (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 a 110 step overlap limit.

TODI NFM0100050 Rexv. I Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA Figure 2.5.1:

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

I.. 140 120 0

cIL U,.

0 100 80 0

,x 60 40 20 0

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

TODI NFM0100050 Rev. I Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 2.6 Heat Flux Hot Channel Factor (FQ(_) (LCO 3.2.1) 2.6.1 F RTP FQ(Z) <Q xK(Z) forP<0.5 0.5 F RTP Fo(Z) <2 T xK(Z) for P>0.5 P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FgTP = 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 951, 4000, 10000, and 18000 MWD/MTU.

For this cycle, the FCQ(z) penalty factors are equal to 2% per 31 Effective Full

-Power Days (EFPD). These values shall be used to increase the FwQ(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups.

Multiplication Factor = 1.02

2.6.3 Uncertainty

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

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is Inoperable Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

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

TODI NFM0100050 Rev. I Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I OA Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.1 (0.0, 1.0) (6.0, 1.0)

(12.( ,0.924) 0.9 0.8 N0.7 LL

  • 0 S0.6 E

0 0.5 Z

S"4LOCA Limiting .

ý- 0.4 Envelope _

0.3 0.2 0.1 0

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

TODI NFM0100050 Rev. I Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA Height MAX W(Z)

Feet Byron Unit 2 Cycle 10A 0.00 1.0000 0.20 1.0000 Figure 2.6.2.a 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 951 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1 20 1.0000 1.40 I 0000 1.60 1.0000 1.40 1.80 1.1899 2.00 1.1789 2.20 1.1656 2.40 1.1546 2.60 1.1413 4 2.80 1.1300 3.00) I 1187 1.35 3.20 1.1054 3.40 1.0944 3.60 1.0941 3.80 1.0959 4.00 .0974 4.20 1.0984 1.30 4.40 1.0999 4.60 1.1008 4.80 1.1007 5.00 1.1006 5.20 1.0997 5.40 1.0978 5.60 1.1086 z 1.25 5.80 1.1259 1.1432 0I _ -4 6.00 6.20 1.1597 z 6.40 1.1754 L.

6.60 1.1901 4 6.80 1.2028

__________ __________ 4 __________

7.00 1.2146 1.20 7.20 1.2234 ---

7.40 1.2329 7.60 1.2403 4 7.80 1.2488 4

8.00 1.2555 8.20 1.2590 4 1.15 8.40 1.2647 8.60 1.2696 8.80 1.2754 1.2794 4 9.00 9.20 1-2825 9.40 1.2979 9 4

9.60 1.3224 1.10 9.80 1.3388 10.00 1.3480 10.20 1-3614 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1i I1.20 1.0000 0.00 2.00 4.00 6.00 8.( 00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFMO100050 Rev. I Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1OA Height MAX W(Z) 1Feet Byron Unit 2 Cycle IOA 0.00 1.0000 0.20 1.0000 Figure 2.6.2.b 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 4000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216)

S.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.8(0 2.00 1.2096 1.1952 1.40 r r I 1 2.20 1.1775 2.40 1.1623 2.60 1.1456 2.80 1.1309 3.00 1.1158 1.35 3.20 1.0997 -I 3.40 1.0913 3.60 1.0922 3.80 1.0930 4.00 1.0929 4.20 1.0928 _ _ ~ 4 +/-~v 1.30 4.40 1.0917 4.60 1.0887 ,4.

4.80 1.0874 5.00 1.0853 5.20 1.0821 5.40 1.0790 5.60 1.0812 z 1.25 5.80 1.0996 6.00 1.1170 6.20 1.1348 z 6.40 1.1515 1A.1 6.60 1.1672 6.80 1.1809 7.00 1.1975 1.20 7.20 1.2152 7.40 1.2294 7.60 1.2434 7.80 1.2567 8.00 1.2669 8.20 1.2752 1.15 8.40 1.2813 8.60 1.2876 8.80 1.2911 9.00 1.2927 9-20 1.3005 9.40 1.3189 9,60 1.3405 1.10 9.80 1.3540 10.00 1.3650 10.20 13813 10.40 1.0000 10.60 1.0000 10.80 1.0000 I1.00 1.0000 1.05 - I A. A. I I1.20 1.0000 0.0 0 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFM0100050 Rev. I Page 10 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA Height MAX W(Z)

Feet Byron Unit 2 Cycle I0A 0.00 1.0000 0.20 1.0000 Figure 2.6.2.c 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 10000 MWD/MTU 0.80 1.0000 (lop and Bottom 15%Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1 0000 1.30 1.80 1.2549 2.00 1.2369 2.20 1.2174 2.40 1.2089 2.60 1.2012 2.80 1.1941 3.00 1.1863 3.20 1.1771 3.40 1.1680 3.60 1.1560 3.80 1.1459 4.00 1.1349 1.25 4.20 1.1261 4.40 1.1183 4.60 1.1100 4.80 1.1020 5.00 1.1014 5.20 1.1020 5.40 1.1036 5.60 1.1033 z

5.80 1.1029 0 6.00 1.1115 6.20 1.1212 2 1.20 6.40 1.1310 6.60 1.1378 6.80 1.1437 7.00 1.1513 7.20 1.1590 7T40 1.1676 7.60 1.1738 7.80 1.1778 8.00 1.1806 8.20 1.1827 8.40 1.1843 8.60 1.1811 1.15 8.80 1.1806 9.00 1.1778 9.20 1.1836 9.40 1.1929 9.60 1.1993 9.80 1.2175 10.00 1.2370 10.20 1.2527 10.40 1.0000 10.60 1.0000 10.80 I.0000 11It*

11.00 1.0000 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 1.0000 CORE HEIGHT (FEET) 11.60 11.80 1.0000 12.00 1.0000

TODI NFM0100050 Rev. I Page 1 Iof 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA Height MAX W(Z)

Feet Byron Unit 2 Cycle I0A 0.00 1.0000 0.20 1.0000 Figure 2.6.2.d 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 18000 MWD/MTU 0.80  !.0000 (Top and Bottom 15% Excluded per WCAP- 10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.30 -Y I 1" Y I 1.80 1.2870 2.00 1.2714 2.20 1.2558 2.40 1.2433 2.60 1.2290 2.80 1.2156 3.00 1.2012 3.20 1.1872 3.40 1.1892 3.60 1.1896 3.80 1.1901 4.00 1.1898 1.25 4.20 1.1880

  • 4.40 1.1844 4.60 1.1776 4.80 1.1790 5.00 1.1840 5.20 1.1876 5.40 1.1900 5.60 1.1926 z

5.80 1.2074 0I 6.00 1.2197 6.20 1.2295 1.20 6.40 1.2381 6.60 1.2430 6.80 1.2452 - -*- _

7T00 1.2446 *

  • 7 20 1.2392 7.40 1.2332 4 7.60 1.2227 7.80 1.2122 4 8.00 1.1984 8.20 1.1810 8.40 1.1663 8-60 1.1519 1.15 _________ 4 _________

8.80 1.1437 4

9.00 1.1419 4 9.20 1.1391 4 9.40 1.1362 9.60 1.1790 9.80 1.2170 10.00 1.2520 10.20 1.2840 10.40 1.0000 10.60 1.0000 10.80 1.0000 I1.00 1.0000 1.10 11.20 1.0000 0.0 0 2.00 4.00 6.00 8.00 10.00 12.00 I1.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFMO100050 Rev. I Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNH) (LCO 3.2.2)

N<F TP~j0+P 2.7.1 FAH - FaN[1.0 + PFAH(l .0 - P)]

where: PFRTP= the ratio of THERMAL POWER to RATED THERMAL POWER FA= 1.70 PFAH = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FAHN shall be calculated by the following formula:

UFAH = UFAHm where:

UFHm = Base FNH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNAH Warning Setpoint > 2% of FNAH Margin FNH Alarm Setpoint >_0% of F NH 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 Acceptable Operation Limits are applicable.

2.9 Departure from Nucleate Boilinq Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL > 1.659 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER

_>50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

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

TODI NFMO100050 Rev. I

--- Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1OA Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power MalFu Ruffebren Units cyde Bimp > 6000 IVIOMfl 120 0

60 40-30-20 -10 0 10 20 30 40 50 AXUML jFUX UFM4 (0/4

TODI NFM0100050 Rev. I Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 2.10 Reactor Trip System Overtemperature AT Setpoint Parameter Values (LCO 3.3.1) 2.10.1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint Ta 2 gcoefficient K2 shall be equal to 0.0297 / OF.

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

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 587.0 OF.

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

2.10.6 The measured reactor vessel AT lead/lag time constant t1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel AT lag time constant t 3 shall 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 t 5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant t6 shall be less than or equal to 2 sec.

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

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

TODI NFM0100050 Rev. I Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 10A 2.11 Reactor Trip System Overpower AT Setpoint Parameter Values (LCO 3.3.1) 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 / OF for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / OF for decreasing Tavg 2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / OF when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / OF when T < T".

2.11.6 The nominal TaVg at RTP (indicated) T" shall be less than or equal to 587.0 OF.

2.11.7 The measured reactor vessel AT lead/lag time constant 'r1 shall be equal to 8 sec.

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

2.11.9 The measured reactor vessel AT lag time constant "r3 shall be less than or equal to 2 sec.

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

2.11.11 The measured reactor vessel average temperature rate/lag time constant t7 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 (A1) "negative" slope shall be 0 for all Al.

TODI NFM0100050 Rev. I Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE IOA 2.12 Reactor Coolant System (RCS) DNB Parameter 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 592.1 OF.

2.12.3 The RCS total flow rate shall be greater than or equal to 380,900 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 2000 ppm (LCO 3.9.1).

2.13.2 The Reactor Coolant System boron concentration shall be greater than or equal to 1918 ppm at all 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 (TLCO 3.1.g and TLCO 3.1.k)

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