BYRON 2008-0031, Cycle 16 Core Operating Limits Report

Cycle 16 Core Operating Limits Report

ML080980328
Person / Time
Site:	Byron
Issue date:	04/04/2008
From:	Hoots D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.01.0700, BYRON 2008-0031
Download: ML080980328 (17)

Text

April 4, 2008 LTR: BYRON 2008-0031 File: 2.01.0-700 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 16 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

we are submitting the Unit 1 COLR Revision 5 for Cycle 16.

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

Attachment:

Byron Station Unit 1 Cycle 16 COLR, Revision 5 cc: Regional Administrator - NRC Region Ilf NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety

Manager of Energy Practice - Winston & Strawn Site Vice President - Byron Station Vice President - Licensing & Regulatory Affairs Director - Licensing Manager - Licensing and Compliance - Braidwood & Byron Stations Regulatory Assurance Manager - Byron Station Exelon Document Control Desk Licensing (Hard Copy)

Exelon Document Control Desk Licensing (Electronic Copy)

PWR Supervisor - Nuclear Fuels Management Supervisor - Byron Reactor Engineering

ATTACHMENT Byron Station Unit 1 Core Operating Limits Report Revision 5 Cycle 16

NF'-CB-08-29 February 8,2008 CORE OPERATING LlMlTS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 16 EXELON TRACKING ID:

COLR BYRON 1 REVISION 5

COLR BYRON 1 Revision 5 Page 1 of 13 CORE OPERATmG LIMITS =PORT (COLR) for BYRON UNrr 1 CYCLE 16 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 16 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)

LC0 3.1 .I SHUTDOWN MARGIN (SDM)

LC0 3.1.3 Moderator Temperature Coefficient (MTC)

LC0 3.1.4 Rod Group Alignment Limits LC0 3.1.5 Shutdown Bank lnsertion Limits LC0 3.1 -6 Control Bank Insertion Limits LC0 3.1.8 PHYSICS TESTS Exceptions MODE 2-LC0 3.2.1 Heat Flux Hot Channel Factor (Fcl(Z))

LC0 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F ~ , ~ )

LC0 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LC0 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LC0 3.3.1 Reactor Trip System (RTS) Instrumentation LC0 3.3.9 Boron Dilution Protection System (BDPS)

LC0 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and FIow Departure from Nucleate Boiling (DNB) Limits LC0 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 2 1.0 TRM TLCO 3.1 .i Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1 .k Position Indication System - Shutdown (Special Test Exception)

COLR BYRON 1 Revision 5 Page 2 of 13 CORE OPERATWG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 16 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 Safe& Limits lSLs) ( S t 2.1 .I) 2.1.1 In MODES 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shali not exceed the limits specified in Figure 2.1.1.

Fraction. . of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON I Revision 5 Page 3 of 13 G O E OPERATING LlMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 16 2.2 SHUTDOWN MARGIN lSDMl The SDM limit for MODES l,2, 3, and 4 is:

2.2.1 The SDM shall be greater than or equal to 1.3% Aklk (LCOs 3.1 .I, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRMTLCOs3.l.b, 3,l.d, 3.l.f, 3.l.h,and3,l.j).

The SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% Auk (LC0 3.1.1, LC0 3.3.9; TRM TLCOs 3.1 .iand 3.1.j).

2.3 Moderator Temperature Coefficient (MTCI (LC0 3.1 -3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOUARO/HZP-MTC upper limit shall be +2.087 x 10'~ Aklkl°F.

2.3.2 The EOUAROIHFP-MTC lower limit shall be -4.6 x 1004A W F .

2.3.3 The EOUAROIHFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 1 AW°F 2.3.4 The EOUAROIHFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10" AWkl°F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LC0 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.

2.5 Control Bank Insertion Limitg (LC0 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 bs 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:

COLR BYRON 1 Revision 5 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 16 Figure 25.1 :

~~&

mtrd Bank Inserfion Urnits V e r s ~ ~ s t d M Paw 0 10 20 30 40 5Q 60 70 80 90 $00 R e l a t i v e Power ( P e r c e n t )

GOLR BYRON 1 Revision 5 Page 5 of 13 C O m OPERATING LIMITS =PORT (COLR) for BYRON UNIT 1 CYCLE 16 2.6 Heat Flux Hot Channel Factor IF& (LC0 3.2.1) 2.6.1 Total Peaking Factor:

F,RTP F,,(Z) 5 - x K ( Z ) forP>O.S P

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

bf When PDMS is inoperable, W(Z) is provided in Table 2.6.2.a.

The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.

Table 2.6.2.b shows the ~ ' ~ ( 2penalty

) factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the ~ ~ ~as( per 2 )

Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.b.

2.6.3 Uncertainty

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

U, = Base Fa measurement uncertainty = 1.05 when PDMS is inoperable (U,, is defined by PDMS when OPERABLE.)

U, = Engineering uncertainty factor = 1.03 2'6.4 PDMS Alarms:

Fa@) VVarning Setpoint 2 2% of Fo(Z) Margin FafZ) Alarm Setpoint 2 0% of Fa(Z) Margin

COLR BYRON 1 Revision 5 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 16 Figure 2.6.1 K(2) Normalized FG(Z)as a Function of Core Height 0 1 2 3 4 5 6 7 8 9 1 0 1 1 1 2 BOTTOM Core Height (ft) TOP

COLR BYRON I Revision 5 Page 7 of 13 CORE OPERATING LIMITS REPORT (GOLR) for BYRON UNIT 1 CYCLE 16 WfZ) versus Core Height Note: WfZ) values at 20000 UWDIMTU may b e applied to cycle burnups greater than 20000 MWDlMTU to prevent W ( Z f function extrapolation

COLR BYRON 1 Revision 5 Page 8 of 13 CORE?OPERATING LIMITS REPORT (COLR) for BYRON UNI?' I CYCLE 16 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.

COLR BYRON 1 Revision 5 Page 9 of 13 CORE OPEMTINC LIMITS =PORT (COLR) for BYRON UNIT I CYCLE 1G 2.7 Nuclear Enthalov Rise Hot C h a n n e l (LC0 3.2.2) 2.7.1 F~~~ -

I e i P [ l-0 + PFM(l .O P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F%' = 1-70 PFw = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFM, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor fNA" shall be calculated by the following formula:

where:

U F ~= H ~

Base measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNMWarning Setpoint 2 2% of F~~~Margin FNAH Alarm Setpoint 2 0% of FNAH Margin 2.8 AXIAL FLUX DIFFERENCE fAFD1 (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 De~arturefrom Nucleate Boilina Ratio (DNBR) (LC0 3.2.5)

The Axial Power Shape Limiting DNBR ( D N B R A ~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

COLR BYRON I Revision 5 Page 10 of 13 CORE! OPERATNG LIMITS WPORT (GOLR) for BYRON ?JNIT I CYCLE 16 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits I with PDMS Inoperable I

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

1

COLR BYRON 1 Revision 5 Page 11 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON WIT 1 CYCLE 16 2.f 0 -

Reactor Trip Svstem lRTSf Instrumentation (LC0 3.3.1) Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint Kishall be equal to I .325.

2.10.2 The Overtemperature AT reactor trip setpoint TavGcoefficient K2shalt be equal to 0.0297 IO F .

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3shall be equal to 0.00181 1 psi.

2.10.4 The nominal T a,t, RTP (indicated) T' shall be less than or equal to 588.0 O F .

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

2.1 0.6 The measured reactor vessel AT leadllag time constant T, shall be equal to 8 see.

2.10.7 The measured reactor vessel AT leadllag time constant z2shalIbe equal to 3 sec.

2.10.8 The measured reactor vessel AT lag time constant ~ ~ s h abet lless than or equal to 2 sec.

2.1 0.9 The measured reactor vessel average temperature leadhag time constant z4 shall be equal to 33 sec.

2.1 0.10 The measured reactor vessel average temperature leadhag time constant 5 shall be equal to 4 sec, 2.10.1 1 The measured reactor vessel average temperature lag time constant z6shall be less than or equal to 2 sec.

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

2.10.13 The f, (At) "negative" breakpoint shall be -18% dl.

2.10.14 The f, (Al) 'positive" slope shall be c3.47% 1% Al.

2.10.15 The f, (Al) "negative" slope shall be -2.61% f % dl.

COLR BYRON 1 Revision 5 Page 12 of 13 COW OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 16 2.11 Reactor Trio Svstem (RTS) Instrumentation (LC0 3.3.1) - Overpower AT Setpoint Parameter Values 2.1 1.1 The Overpower AT reactor trip setpoint Kq shall be equal to 1.072.

2.1 1.2 The Overpower AT reactor trip setpoint,T, rateflag coefficient Kgshall be equal to 0.02IO F for increasing . ,T 2.11.3 The Overpower AT reactor trip setpoint TavQ rateflag coefficient Ks shafl be equal to 0 / "F for decreasing,,,T, 2.11.4 The Overpower AT reactor trip setpoint TaVQ heatup coefficient Kg shall be equal to 0.00245IO F when T > T".

2.1 1.5 The Overpower AT reactor trip setpoint TavQ heatup coefficient K6 shall be equal to OI°FwhenTIT".

2.11.6 The nominal Tav,at RTP (indicated) T" shall be less than or equal to 588.0 O F 2.11.7 The measured reactor vessel AT leadllag time constant z, shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT leadllag time constant z2shall be equal to 3 sec.

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

2.11 .I0 The measured reactor vessel average temperature lag time constant zeshall be less than or equal to 2 sec.

2.1 1.11 The measured reactor vessel average temperature ratellag time constant T, shall be equal to 10 see.

2.1 1 .I2 The f2 (Al) "positive" breakpoint shall be 0 for all Al.

2.j1 .I3 The f2(Al) "negative" breakpoint shall be 0 for all AI.

2.1 1-14 The f2 (Ai) "positive" slope shall be 0 for all At.

2.11.15 The f2 (A!) "negative" slope shall be 0 for all dl.

COLR BYRON 1 Revision 5 Page 13 of 13 GORE OPEMTLNG LIMITS REPORT (COLR)for BYRON UNrI I CYCLE 16 2.12 Reactor Coolant Svstem (RCS) Pressure, Temoerature, and Flow Deaarture from Nucleate Boilinu (DNB) Limits (LC0 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 (TavQ) shalt be less than or equal to 593.1 O F .

2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.

2.1 3 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the value given in the Table below (LC0 3,9.1), The reported value also bounds the end-of-cycle requirements for the previous cycle.

2,132 To maintain keff 50.987 with all shutdown and control rods fully withdrawn in MODES 3,4, or 5 (TRM TLCO 3.1 .g Required Action 8.2 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.

I COLR Conditions Boron Concentration Section (PP~) I 2.13.1 Refueling 1741 2.13.2 a) prior to initial criticality 1 796 2.13.2 b) all other times in life 1995