BYRON 2002-0023, Revision 3 to Cycle 11A Core Operating Limits Report

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Revision 3 to Cycle 11A Core Operating Limits Report
ML020730014
Person / Time
Site: Byron  Constellation icon.png
Issue date: 02/27/2002
From: Lopriore R
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2002-0023
Download: ML020730014 (18)
v • d • e


Text

Exelon.

Exelon Generation Company, LLC www.exeloncoTp.com Nuclear Byron Station 4450 North German Church Road Byron, IL 61010-9794 February 27, 2002 LTR: BYRON 2002-0023 File: 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:

Revision 3 to Byron Station Unit 1 Cycle 1 1A Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

we are submitting Revision 3 to the Unit 1 COLR. The Unit 1 COLR was revised to specify the power distribution transient function (i.e., W(z)) for cycle burnup of 18000 MWD/MTU and beyond.

Please note that Revision 2 of the COLR was issued but not implemented due to Plant Review comments. These comments were addressed and incorporated into Revision 3.

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

Respectfully, qcard P.Lpir Site Vice President Byron Nuclear Generating Station

Attachment:

Byron Station Unit 1 Cycle 11 A COLR, Revision 3 RPL/JL/dpk cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

ATTACHMENT I Byron Station Unit I Cycle 11A Core Operating Limits Report Revision 3

NUCLEAR FUEL MANAGEMENT DEPARTMENT TRANSMITTAL OF DESIGN INFORMATION

[ SAFETY RELATED Originating Organization NFM ID# NFMO100048 C NON-SAFETY RELATED [ Nuclear Fuel Management Rev. No. 3 C REGULATORY RELATED C Other (specitf') Page 1of 16 Station Byron Unit I Cycle ]I A Generic To: Ronald J. Niederer- Byron Subject Byron Unit I Cycle I IA Core Operating Limits Report in ITS Format and W(z) Function Brian L. Manges Z o,7

_7/ bz_

Preparer Prep r's Signature V Date Tyrone L. Stevens ~

Reviewer Revi g Date R. Tsai 1-6 2-*/

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

Description of Information:

Attached is the Byron Unit I Cycle 1IA Core Operating Limits Report (COLR) in the ITS format and W(z) function. This COLR is for uprate at 3586.6 MWt. Revision 3 of this TOD[ supercedes Revision 2.

Purpose of Information:

In Revision 3, the wording for Item 2.6.2 will be revised to say "W(z) values have been specified for bumups of". This is only a wording change to more clearly describe the change. In Revision 2, the W(z) factors were revised to eliminate the overly conservative extrapolation of the W(z) factors past 18000 MWD/MTU. The same set of W(z) factors are provided at 17000, 18000, 22000, and 25000 MWD/MTU (Reference 6). In Revision I, 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:

1. Westinghouse Letter O CB-G-057 (CAC-01-104), dated April 6, 2001
2. TODI NFM0000188, Sequence 0 "Pressurizer Pressure DNB Limit", A. W. Wong to D. Wozniak and T. Luke, December
15. 2000
3. Westinghouse Letter OICB-G-047 (ASD-01-90), dated March 23, 2001
4. Westinghouse Letter CAC-01-123, 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
6. Westinghouse Letter NF-CB-02-2 (CAC-02-1 0), January 1I, 2002 Supplemental Distribution: P. E. Reister / J. E. Langan (BY)

TODI NFM0100048 Rev. 3 Page 2 of 16 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 I1A 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 (FN,1H)

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. 3 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 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 psi3 660 2250 psia La_

640 E

620 Q) 600 580 0 -.2 .4 6. 2 Froction of Nominol Power Figure 2.1.1: Reactor Core Limits

TODI NFM0100048 Rev. 3 Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA 2.2 Shutdown MarQin (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" 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 1 0 ' 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 NFMO100048 Rev. 3 Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I I A Figure 2.5.1:

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

'A 140 CL 120 "0

C.

100 (U

IA W

0*

0 80 60 40 20 0

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

TODI NFMO100048 Rev. 3 Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA 2.6 Heat Flux Hot Channel Factor (F(Z.)) (LCO 3.2.1) 2.6.1 FRTP FO(Z) < *. xK(Z) for P*_< 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 F0 TP = 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 specified for burnups of 17000, 18000, 22000, and 25000 MWD/MTU.

For this cycle, the F C(z) penalty factors are equal to 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWe(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 .Q = Ua 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 FQ(Z) Margin FQ(Z) Alarm Setpoint > 0% of Fo(Z) Margin

TODI NFMO100048 Rev. 3 Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I I A Figure 2.6.1 K(Z) - Normalized Fo(Z) as a Function of Core Height 1.1-----------------

(0.0, 1.0) (6.0,1.0)

(12.C,0.924) 0.9 0.8--

  • i 0.7 a

LL "O 0.6-E 0 0.5 z

LOCA Limiting 00.4--

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 NFMO100048 Rev. 3 Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I I A 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 17000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-102161 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.45 7 - 7 -

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 "*(t

!  :. 9 5.80 1.2449 z 0

6.00 1.2585 6.20 1.2681 z * - 4 ___

6.40 1.2757 6.60 1.2774 6.80 1.2782 4 4 7.00 1.2768 1.25 7.20 1.2733 i  : i 4-4--

7.40 1.2679 4 ________

7.60 1.2571 7.80 1.2469

  • !* ii4 - i -*

8.00 1.2337 8.20 1.2186 4i *  :

1.20 8.40 1.2047 8.60 1.1922 8.80 1.1965 4o 9.00 1.2001 9.20 1.2363 9.40 1.2828 i l *:4 9.60 1.3274 1.15 9.80 1.3669 10.00 1.A026 10.20 1.4333 10.40 1.0000 10.60 1.0000 10.80 1.0000 1 10l 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 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFM0 100048 Rev. 3 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I I A Height MAX W(Z)

Feel Byron Unit 1 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 18000 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 1.45 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 4-40 1.35 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 !i  !

z 1.30 5.80 1.2449 0 9i 6.00 1.2585 L..

6.20 1.2681 6.40 1.2757 Ll S".

! i! i

  • i j  :

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 1000 1.4026 10-20 10.40 10.60 1.4333 1.0000 1.0000

_ _ i _ _ I _ I _ _ I _

10.80 1.0000 t 1- t a 11.00 1.0000 1.10 11.20 L. 000 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. 3 Page 10 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA Height MAX W(Z)

Feel 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 22000 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 1.45 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 0 6.00 1.2585 0P 6.20 1.2681 -4i 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 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

TODI NFMO100048 Rev. 3 Page 11 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE II A Height MAX W(Z)

Feet Byron Unit I Cycle I IA 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 25000 MWD;MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-102161 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 i .! : i i.

5.60 1.2284 1.30 5-80 1.2449 F

6.00 1.2585 6.20 1.2681 z 6.40 1.2757 ----- 4 -* "

!t  :

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 12047 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 I1.00 1.0000 1.10 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)

S1.80 1.0000 12.00 1.0000

TODI NFMO100048 Rev. 3 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE I IA 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN H) (LCO 3.2.2)

RTP 2.7.1 F-H< FAH [1.0 + PFAH(1.0 - 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 FANN shall be calculated by the following formula:

N UFAH UFAHm where:

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

FNAH Warning Setpoint > 2% of FN AH Margin FNAH Alarm Setpoint > 0% of F N6H 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

> 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 NFM0100048 Rev. 3 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I IA Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Aidal RuKEffemrm Units With FEJV I, mpere 120 laD (151 (+10 11m< ,

< 80~ -- If ,tn7

-3l U.1 60j 0-1 3-0 0 0 2 34 40 , 3 0 20 3 -1 n 5 I I -u - -F AXIAL FLLD(DffffUU (o

TODI NFMO100048 Rev. 3 Page 14of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE II A 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 Tmvg 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 Ta g9at 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 T3 shall be less than or equal to 2 sec.

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

2.10.10 The measured reactor vessel average temperature lead/lag time constant C5 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 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 NFM0100048 Rev. 3 Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE I I A 2.11 Reactor Trip System Overpower AT Setpoint Parameter Values (LCO 3.3.1) 2.11.1 The Overpower AT reactor trip setpoint K 4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient 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 Tav.

2.11.4 The Overpower AT reactor trip setpoint Tag 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 588.0 OF.

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

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

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

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

2.11.11 The measured reactor vessel average temperature rate/lag time constant "7 shall be equal to 10 sec.

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

2.11.13 The f2 (AI) "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 (A*) "negative" slope shall be 0 for all Al.

TODI NFMO100048 Rev. 3 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 1 IA 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 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 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)

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