ML090970911

Core Operating Limits Report, Unit 1, Cycle 15

ML090970911
Person / Time
Site:	Braidwood
Issue date:	04/07/2009
From:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW090034
Download: ML090970911 (15)

Text

April 7, 2009 BW090034 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 15 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 15, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 1 Cycle 15 COLR, Revision 7 was implemented during Braidwood Unit 1 Refueling Outage 14 in support of Cycle 15 operation. Note that Revision 7 is the original version of the Braidwood Unit 1 Cycle 15 COLR implemented in support of Cycle 15 operation. The revision number is based on a numbering convention that continues from the previous revision of the Unit 1 COLR, i.e., Braidwood Unit 1 Cycle 14 COLR, Revision 6.

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

Sincerely, ryan Hanson Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report, Braidwood Unit 1 Cycle 15, Revision 7 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station

ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 1 Cycle 15 Revision 7

COLR BRAIDWOOD 1 Revision 7 Page 1 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specifications affected by this report are iisted 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))

Nuclear Enthalpy Rise Hot Channel Factor (F ~H)

N LCO 3.2.2 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 ofthe 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 3.1.1 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 BRAIDWOOD 1 Revision 7 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 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.

6 80 r--'-"-~r----'---r----'-----'----,---"""

6 6 0 -t---.....;::::....."t:::----+----;----.....il-----+----!

La...

0"1 (1) o

............ 6 .. 0 +-----f-----=~::::__---f_---+_-.;;:::..oo:::::__+---_1

~

J

---~

(1) c..

E (1) t-(1) 620 -t--...::o....,~+----~:::::.......:::__-+_---+_---+_~:::--~

0"1

~

(1)

~

600 -+----+-----If------f--~~---_+-..;;::....o:::--_I o .2 ... .6 .8 1 .2 Fraetion of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 1 Revision 7 Page 3 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 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% tlklk (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% tlklk (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i 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 +1.045 x 10-5 tlklkloF.

2.3.2 The EOLIARO/HFP-MTC lower limit shall be -4.6 x 10-4 tlklkloF.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 tlklkloF.

2.3.4 The EOLIARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 tlklkrF.

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 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) 225 110 226 111 227 112 228 113 229 114

COLR BRAIDWOOD 1 Revision 7 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 Figure 2.5.1:

Control Bank Insertion Umits Versus Percent Rated Thermal Power 200 180 +-----.~--+--+_---+--------+-----I+_-----+-----+----r----i

-c

~ 160 T,.,..~-l...-...,+****************************!****************** t********************,,***********+ + + + . (100%, 161) f.':!

"0

.c

~ 140 -I----+-----1---t----¥---r;:;-;;u7.;:::;'1------+-------+------+-~~--I III c.

S 120 C/)

c o

e 100 III o

a.

~ 80 i*********************** + .." + , + ***,*******************************+***"****1*********...... +.... +************************1 Cll aJ "0

/}. 60 40 20 ..***************************

o+---+---+-~~-+--""""""'--+--!----+---+- ......

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

COLR BRAIDWOOD 1 Revision 7 Page 5 of 13 CORE OPERATING LlMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 15 2.6 Heat Flux Hot Channel Factor (Fg,@ (LCO 3.2.1) 2.6.1 Total Peaking Factor:

F RTP FQ(Z) s,~xK(Z) forps,O.5 0.5 F RTP FQ(Z) s, _Q-xK(Z) forP >0.5 P

where: P = the ratio ofTHERMAL POWER to RATED THERMAL POWER F~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 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 Feo(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.b.

2.6.3 Uncertainty

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

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

Ue = =

Engineering uncertainty factor 1.03 2.6.4 PDMS Alarms:

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

COLR BRAIDWOOD I Revision 7 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 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) 1 (12.( .0.924)

"""'I 0.9 0.8 NO.7 a

u.

'tS

.~ 0.6 Ri E

o 0.5 z

N .......- LOCA Limiting ~

~ 0.4 Envelope 0.3 0.2 0.1 o

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

COLR BRAIDWOOD 1 Revision 7 Page 7 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 Table 2.6.2.a WIl) versus Core Height (Top and Bottom 8% Excluded perWCAP-10216)

Height 150 GOOO 1400. 20000 (feet) NMl'DiMlU NMl'DiMTU NMl'DiMTU MWD!MTU 0.00 (core bottom) 1.2956 1.4588 1.4220 1 345~

0.20 1.28~8 1.4254 1.~9n i 3224 oflO 1.2785 1.4116 13809 13122 0.60 1.2717 1.~15 13735 13080 0.90 1.2590 1.~00 13479 13020 1.00 1.2505 1.~73 13324 12990 1.20 1.2420 1.2872 13160 12910 1flO 1.2~89 1.2706 13015 12840 1.60 1.2279 1.2561 12820 12740 1.80 1.2208 1.~58 12671 12650 2.00 1.21~0 1.2172 12573 12550 2.20 1.1952 1.2000 12465 12420 2.40 1.18~8 1.1910 12~62 12290 2.60 1.1667 1.1810 122~1 12140 2.80 1.1540 1.1734 12116 12000

~.OO 1.1522 1.1676 12021 1.1860

~.20 1.1512 1.160~ 1.1935 1.1701

~.4O 1.1501 1.155~ 1.1957 1.1726

~.60 1.1471 1.1502 1.1761 1.1745

~.80 1.1~ 1.1471 1.1709 1.1767 4.00 1.1473 1.1429 1.1658 1.1779 4.20 1.1499 1.1~82 1.1606 1.1786 4.40 1.1515 1.13~5 1.1545 1.1768 4.60 1.1511 1.1265 1.1469 1.1848 4.80 1.1505 1.1204 1.1~97 1.1919 5.00 1.1491 1.1148 1.1~85 1.1971 5.20 1.145~ 1.1099 1.1~96 12019 5.40 1.1417 1.1129 1.1416 12044 5.60 1.1~60 1.1164 1.1422 12240 5.80 1.1~28 1.1209 1.1458 12415 6.00 1.1~85 1.1245 1.1594 12552 6.20 1.1~2 1.1260 1.1711 12668 6.40 1.1469 1.1325 1.1808 12755 6.60 1.1486 1.1429 1.1875 12772 6.80 1.1494 1.15~8 1.19~~ 12779 7.00 1.1492 1.1628 1.1961 12748 7.20 1.1609 1.1700 1.1960 12667 7.40 1 .17~5 1.1756 1.1940 12567 7.60 1.1850 1.1776 1.1890 12427 7.80 1.1958 1.1859 1.18~1 12297 8.00 1.2058 1.19~4 1.1782 1 21~9 8.20 1.2140 1.1956 1.1722 1.1951 8.40 1.222~ 1.2049 1.1673 1.1792 8.60 1.2286 1.212~ 1.1604 1.1708 8.80 1.2~51 1.225~ 1.1586 1.1660 9.00 1.2417 1.2468 1.1649 1.1608 9.20 1.2504 1.2594 1.177~ I 1.1587 9.40 1.2542 1.2722 1.1861 12008 9.60 1.2581 1.2820 1.19~5 12424 9.80 1.2516 1.2928 12080 12809 1000 1.2495 1.~~6 12~60 13166 1020 1.2~ 1.~85 12620 1 348~

1040 1.2411 1.~1~5 12800 13779 10.60 1.2409 1.~17~ 129~9 1.4007 1080 1.2~95 1.~21 13087 1.4185 1100 1.2~~ 1.~77 13185 1.~1~

1120 1.2471 1.~62 1 318~ 1.~92 11.40 1.2521 1.~79 13040 1.4000 11.60 1.2564 1.~54 12992 14171 1180 1.2608 1.~21 12891 1.4089 12.00 (core top) 1.2688 1.~6~ I 129~8 1.4067 Ilote: W(Z) values at 20000 MWD iMTU may be applied to cycle bumups greater than 20000 MWDIMTU to prevent W(Z) function extrapolation

COLR BRAIDWOOD 1 Revision 7 Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 Table2.6.2.b Penalty Factors in Excess <t 2% per 31 EFPD C'yrle Bumup Penally Factor (MVl/DItv1TU) FCa(Z) o 1.035 150 1.035 494 1.056 666 1.063 837 1.068 1009 1.070 1181 1.069 2556 1.023 2728 1.020 14759 1.020 15103 1.021 163(6 1.028 16650 1.029 16822 1.030 16994 1.030 17681 1.029 18541 1.027 18712 1.026 190E6 1.023 19400 1.020 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 BRAIDWOOD 1 Revision 7 Page 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD tJNIT 1 CYCLE 15 N

2.7 Nuclear Enthalpy Rise Hot Channel Factor (F MJ1 (LCO 3.2.2) 2.7.1 FNilH  ::;; F~~P[1.0 + PF ilH (1.0 - P)]

where: P =the ratio of THERMAL POWER to RATED THERMAL POWER F~~P = 1.70 PFilH =0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty. UFilH

• to be applied to the Nuclear Enthalpy Rise Hot Channel Factor N

F ilH shall be calculated by the following formula:

where:

UFLJHm =Base FNilH measurement uncertainty =1.04 2.7.3 PDMS Alarms:

F ilH Warning Setpoint =2% of F ilH Margin N N F ilH Alarm Setpoint =0% of F ilH Margin N N 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 ;:::: 1.536 The Axial Power Shape Limiting DNBR (DNBRAPsd 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

COLR BRAIDWOOD 1 Revision 7 Page 10 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 120 i I I I

(-1~, 10~)

100 D:::

w U nac~epta~le

~ 80 Op~ratioQ

..J ACCelltable

E D:::

w 60 J:

l-e w

~ 40

'0

';fl.

20 o

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

COLR BRAIDWOOD 1 Revision 7 Page 11 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature ~T Setpoint Parameter Values 2.10.1 The Overtemperature ~T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature ~T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/ of.

2.10.3 The Overtemperature ~T 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 of.

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

2.10.6 The measured reactor vessel ~T lead/lag time constant tl shall be equal to 8 sec.

2.10.7 The measured reactor vessel ~T lead/lag time constant t2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel ~T 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 leadllag time constant ts 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 1 (~I) "positive" breakpoint shall be +1 0% ~1.

2.10.13 The f 1 (~I) "negative" breakpoint shall be -18% ~1.

2.10.14 The f 1 (~I) "positive" slope shall be +3.47% / % ~1.

2.10.15 The f 1 (~I) "negative" slope shall be -2.61 % / % ~1.

COLR BRAIDWOOD 1 Revision 7 Page 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 2.11 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overpower liT Setpoint Parameter Values 2.11.1 The Overpower liT reactor trip setpoint ~ shall be equal to 1.072.

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

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

2.11.4 The Overpower liT reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0.00245/ OF when T > T".

2.11.5 The Overpower liT reactor trip setpoint Tavg heatup coefficient Ke 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 liT lead/lag time constant 1:, shall be equal to 8 sec.

2.11.8 The measured reactor vessel liT lead/lag time constant 1:2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel liT lag time constant 1:3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant 1:6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant 1:7 shall be equal to 10 sec.

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

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

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

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

COLR BRAIDWOOD 1 Revision 7 Page 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 15 2.12 Reactor Coolant System (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 (T avg ) 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 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:O; 0.987 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.

COLR Concltions Boron Concentration Section (ppm) 2.13.1 Refueling 1678 2.13.2 a) prior to initial ctiticalily 1764 2.13.2 b) all cthertim es in life '1972