ML053200049

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Core Operating Limits Report, Braidwood, Unit 1 Cycle 12, Revision 3
ML053200049
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 11/07/2005
From: Polson K
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW050101
Download: ML053200049 (17)
v • d • e


Text

Exelon Nuclear Exelon Generation Company, LLC www.exeloncorp.com BTaidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 November 7, 2005 BWO501 01 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 12, Revision 3 The purpose of this letter is to transmit a mid-cycle revision of the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 12, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Item 2.6.2 of the COLR and the corresponding Figures are being revised with newly updated W(z) data, a cycle dependent function that accounts for power distribution transients encountered during normal operation. The updated W(z) data improves the transient peaking factor (FQ) margin. Note that Revision 2 of the COLR was not implemented.

If you have any questions regarding this matter, please contact Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.

Sincerely, Keith J. Polson Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report, Braidwood Unit 1 Cycle 12, Revision 3 cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station fY9O

ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 1, Cycle 12 Revision 3

Revision 3 Page I of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 12 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specifications affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(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) 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 > 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)

Revision 3 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits are applicable for the entire cycle unless otherwise identified. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.

2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1) 2.1.1 In MODES 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.

68(

660 606 1 41-96psi-L..

a)

Cnl sa_

1-ca) 0 620 600 580 2

Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

Revision 3 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.2 SHUTDOWN MARGIN (SDM)

The SDM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).

The SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTCQ (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

0 2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +1.335 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/PF.

0 2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/ F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10"4 Ak/k/0F.

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

2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:

Park Position (step) Overlap Limit (step) 225 110 226 i11 227 112 228 113 229 114

Revision 3 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Figure 2.5.1:

Control Bank Insertion ULmits Versus Percent Rated Thermal Power (27%, 224) (77%, 224) 22e 22(

20(

DBANK 7 18C a

u 16(: (100%,161) 1..

-c m

a) 1C C

0

le10(

0 0

0.b 48(

2C 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

Revision 3 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.6 Heat Flux Hot Channel Factor (FnZg) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

F RTP FQ(Z)

  • Q xK(Z) forP<0.5 0 .5 F RTP FQ(Z) < Q xK(Z) forP >0.5 P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTP = 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 14500, 16000, and 20000 MWD/MTU.

Table 2.6.2 shows the FCQ(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWo(z) as per 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.

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 UFQ = Uql,

  • U, where:

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)

Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

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

Revision 3 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 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) 1I ____ . _ .. . ,a-__(1.

0.924) 0.9 0.8 iZ 0.7 a

U- _ _ ____I_

-- ~~

a) 0.6

-o E

0 5.

N _ __4*LOCA Limiting I I - Envelope I 0.3 0.2 0.1

__ I I I 0

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

Revision 3 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1CYCLE 12 Height MAX W(Z)

Feet Braidwood Unit 1 Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.a 0.40 I.0000 0.60 1.0000 Summary of W(Z) Function at 14500 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 1.35 1.80 1.2817 2.00 1.2618 2.20 1.2362 2.40 1.2190 2.60 1.2000 2.80 1.1904 3.00 1.1780 3.20 1.1648 1.30 3.40 1.1584 3.60 1.1513 3.80 1.1443 4.00 1.1379 4.20 1.1304 4.40 1.1221 4.60 1.1125 4.80 1.1040 1.25 5.00 1.0952 5.20 1.0859 5.40 1.0856 5.60 1.0933 z

5.80 1.1082 0 6.00 1.1238 6.20 1.1368 Z 1.20 6.40 1.1496 L.L 6.60 1.1607 6.80 1.1699 7.00 1.1778 7.20 1.1839 7.40 1.1877 7.60 1.1892 7.80 1.1906 1.15 8.00 1.1888 8.20 1.1841 8.40 1.1817 8.60 1.1841 8.80 1.1877 9.00 1.1906 9.20 1.1905 9.40 1.1913 1.10 9.60 1.1951 9.80 1.2018 10.00 1.2079 10.20 1.2149 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.05 _--

11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 I.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 I.0000 12.00 1.0000

Revision 3 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height MAX W(Z)

Feet Braidwood Unit 1 Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.b 0.40 I.0000 0.60 1.0000 Summary of W(Z) Function at 16000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-1 0216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.40 1.60 1.0000 1.80 1.2949 2.00 1.276 1 2.20 1.2521 2.40 1.2358 2.60 1.2174 2.80 1.2070 1.35 3.00 1.1922 3.20 1.1801 3.40 1.1740 3.60 1.1666 3.80 1.1595 4.00 1.1525 4.20 1.1447 1.30 4.40 1.1358 4.60 1.1254 4.80 1.1160 5.00 1.1068 5.20 1.0970 5.40 1.0961 5.60 1.1035 z 1.25

. 0 5.80 1.1187 I.-

6.00 1.1348 z

6.20 1.1475 6.40 1.1588 6.60 1.1675 izi 6.80 1.1749 3 1.20 7.00 1.1808 7.20 1.1844 7.40 1.1853 7.60 1.1839 7.80 1.1823 8.00 1.1787 8.20 1.1716 1.15 8.40 1.1668 8.60 1.1660 8.80 1.1683 9.00 1.1694 9.20 1.1674 9.40 1.1674 1.1729 1 1.10 9.60 9.80 1.1852 10.00 1.1956 10.20 1.2068 10.40 1.0000 10.60 1.0000 10.80 1.0000 1.05 0-11.00 1.0000 0 .00 2.00 4.00 6.00 8.00 10.00 12.00 11.20 1.0000 11.40 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 I.0000 12.00 1.0000

Revision 3 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height MAX W(Z)

Feet Braidwood Unit 1 Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.c 0.40 I.0000 0.60 1.0000 Summary of W(Z) Function at 20000 MWD/MTU 0.80 I.0000 (Top and Bottom 15% Excluded per WCAP-1 0216) 1.00 I.0000 1.20 I .0000 1.40 1.0000 1.60 1.0000 1.35 1.80 1.2788 2.00 1.2610 2.20 1.24 13 2.40 1.2270 2.60 1.2111 2.80 1.1957 3.00 1.1787 3.20 1.1785 1.30 3.40 1.1795 3.60 1.1780 3.80 1.1769 4.00 1.1739 4.20 1.1698 4.40 1.1651 4.60 1.1583 4.80 1.1544 1.25 5.00 1.1576 5.20 1.1597 5.40 1.1612 5.60 1.1679 5.80 1.1817 z

0 6.00 1.1975 6.20 1.2093 6.40 1.2203 Z 1.20 U-N 6.60 1.2265 6.80 1.2328 7.00 1.2355 7.20 1.2342 7.40 1.2308 7.60 1.2239 7.80 1.2157 1.15 8.00 1.2063 8.20 1.1924 8.40 1.1797 8.60 1.1658 8.80 1.1656 9.00 1.1664 9.20 1.1645 9.40 1.1641 1.10 9.60 1.1770 9.80 1.2136 10.00 1.2471 10.20 1.2786 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.05 L.

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 I.0000 Note: Figure 2.6.2.c may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation.

Revision 3 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) F Q(Z) 668 1.0200 841 1.0229 1013 1.0271 1186 1.0300 1359 1.0311 1877 1.0325 2395 1.0314 2567 1.0310 2740 1.0307 3258 1.0303 3431 1.0298 3776 1.0273 3949 1.0250 4121 1.0220 4294 1.0200 14136 1.0200 14309 1.0203 14481 1.0205 14654 1.0203 14827 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

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

Revision 3 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAN) (LCO 3.2.2) 2.7.1 FNAH < FRTP [1.0 + PFAH(1.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FRAT = 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 FNAH shall be calculated by the following formula:

UFAH = UFAHm where:

UFmH, = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FNAH Warning Setpoint 2 2% of FNH Margin F AH Alarm Setpoint 2 0% of FNAH 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 2 1.536 The Axial Power Shape Limiting DNBR (DNBRApSL) is applicable with THERMAL POWER

Ž 50% RTP when POMS is OPERABLE.

2.9.2 PDMS Alarms:

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

Revision 3 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits w ith PDIMVS Inoperable 120 1 00 W

0

a. 80

-j 2U 60 40 0

20 0

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

Revision 3 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 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 Tav9 coefficient K2 shall be equal to 0.0297/'F.

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

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less 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 T. 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 T3 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 r5 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 f1 (Al) "positive" slope shall be +3.47% / % Al.

2.10.15 The f1 (Al) "negative" slope shall be -2.61% / % Al.

Revision 3 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.

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

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

2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / 'F when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / 0F 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 r6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant1 shall be equal to 10 sec.

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

2.11.13 The f2 (Al) "negative" breakpoint shall be 0 for all Al.

2.11.14 The f2 (Al) "positive" slope shall be 0 for all Al.

2.11.15 The f2 (Al) "negative" slope shall be 0 for all Al.

Revision 3 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.12 Reactor Coolant Svstem (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.

2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 593.1 'F.

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

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the value given in the Table below (LCO 3.9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle.

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

COLR Conditions Boron Concentration Section (ppm) 2.13.1 Refueling 1781 2.13.2 a) prior to initial criticality 1871 2.13.2 b) all other times in core life 2066

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