BW090111, Core Operating Limits Report, Cycle 15
| ML092960502 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/23/2009 |
| From: | Shahkarami A Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW090111 | |
| Download: ML092960502 (16) | |
Text
E October 23, 2009 BW090111 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Core Operating Limits Report, Braidwood Unit 2 Cycle 15 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 15, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR).
Braidwood Unit 2 Cycle 15 COLR, Revision 4 was implemented during Braidwood Unit 2 Refueling Outage 14 in support of Cycle 15 operation. Note that Revision 4 is the original version of the Braidwood Unit 2 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 2 COLR, Le., Braidwood Unit 2 Cycle 14 COlR, Revision 3.
If you have any questions regarding this matter, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.
Sincerely, Amir Shahkarami Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 2 Cycle 15, Revision 4 cc:
NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station
ATTACHMENT Core Operating Limits Report Braidwood Unit 2 Cycle 15 Revision 4
NF-CB-09-135 Rev.3 September 21, 2009 CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 2 CYCLE 15 EXELON TRACKING ID:
COLR BRAIDWOOD 2 REVISION 4
COLR BRAIDWOOD 2 Revision 4 I of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 1.0 CORE OPERATING LIMITS REPORT PHYSICS TESTS Exceptions - MODE 2 Heat Flux Hot Channel Factor (Fa(Z))
Nuclear Enthalpy Rise Hot Channel Factor (FN<lH)
AXIAL FLUX DIFFERENCE (AFD)
Departure from Nucleate Boiling Ratio (DNBR)
Reactor Trip System (RTS) Instrumentation Boron Dilution Protection System (BOPS)
Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Boron Concentration This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 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 listed below:
Reactor Core Safety Limits (SLs)
Moderator Temperature Coefficient (MTC)
Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits SL 2.1.1 LCO 3.1.1 LCO 3.1.3 LCO 3.1.4 LCO 3.1.5 LCO 3.1.6 LCO 3.1.8 LCO 3.2.1 LCO 3.2.2 LCO 3.2.3 LCO 3.2.5 LCO 3.3.1 LCO 3.3.9 LCO 3.4.1 LCO 3.9.1 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 3.1.1 Borated Water Sources - Operating TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.1 Position Indication System - Shutdown Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff?:: 1.0 Shutdown Margin (SDM) - MODE 5 TRM TLCO 3.1.j TRM TLCO 3.1.k Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)
COLR BRAIDWOOD 2 Revision 4 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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.
680 -r------,r-----'-----r----...------,-----r------,
660 +--.......;:::::.......Ii:::-----+----+----+----I-----I l.J...
O'l Q.)
o-- 6.. 0 -t----+---==~::__--_+---_t-.--;;:::a......:~+---__1
~
- J
~
Q.)
c::::a..
E Q.)
t-6 20 +--'::O""~+----~::......::::__--1I__--_t---_+~-...::::--.....l4 Q.)
O'l
~
Q.)
.J:
6 00 +----+----+----f---.......d----+-.......;::~:__f o
.2
.4
.6
.8 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits 1.2
COLR BRAIDWOOD 2 Revision 4 Page 3 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 2.2 SHUTOOWN 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% L'iklk (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.]).
The SDM limit for MODE 5 is:
2.2.2 SDM shall be greater than or equal to 1.3% L'iklk (lCO 3.1.1, lCO 3.3.9; TRM TlCOs 3.1.i and 3.1.]).
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 +1.501 x 10.5 L'iklkl°F.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10-4 L'iklkloF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10.4 L'iklkl"F.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 L'iklkloF.
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) 11
COLR BRAIDWOOD 2 Revision 4 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 Figure 2.5.1:
Control Bank Insertion Umits Versus Percent Rated Thennal Power 224 220 200 180 I
~~,
c:! 160 l'r--~-.., +
..."~ 140
.s 120 r.n-c:o;e 100 Ino Q.
~
80 ClIm
"& 60 40 20 (27%, 224)
(77%,224)
(100%,161) 90 100 80 70 60 50 40 30 20 10 O..--_+_---+--~~-_+_-_+_-_+_--_+_-_+_-_+_-__I o
Relative Power (Percent)
COLR BRAIDWOOD 2 Revision 4 5 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 2.6 Heat Flux Hot Channel Factor (F~ (LCO 3.2.1) 2.6.1 Total Peaking Factor:
xK(Z) for P 0.5 0.5 xK(Z) for P > 0.5 P
where: p:::
the ratio of THERMAL POWER to RATED THERMAL POWER 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 Fea(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWa(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 Fa(Z) shall be calculated by the following formula u
where:
Uqu ::: Base Fa 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:
Fa(Z) Warning Setpoint::: 2% of Fa(Z) Margin Fa(Z) Alarm Setpoint::: 0% of Fa(Z) Margin
COLR BRAIDWOOD 2 Revision 4 6 of 13 CORE OPERATlNG LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height 0.924) 9 10 11 12 TOP 3
4 5
6 7
8 Core Height (ft)
(0.0 1.0)
(6.0 1.0)
(12,(.
I
!=~OCA Limiting '--
Envelope o012 BOTTOM 0.1 0.3 1.1 0.8 0.9 0.2 NO.7 a
LL i
0.6 "iiE o
0.5 z
N:;z 0.4
COLR BRAIDWOOD 2 Revision 4 7 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 Table 2.6.2.a W(Zl versus Core Height (Top and Bottom 8% Excluded per WCAP-10216)
Height f~ 3=
6000 14000 20000 (feet)
MWO/MTU MWO/MTU MWOIMTU MWO/MTU 000 (co", tloltom) 1.4576 104652 13512=i 020 12742 104271 104373 13481 0.40 12848 1.4103 1.4203 13390 0.00 12580 13955 104043 1.3342 0.00 12538 13734 1.3003 13287 1.00 1.2503 1.3558 13837 1.3233 120 12314 1.3358
+
1.3349 13141 1040 12358 1.3289 1.3186 13056 100 1.2411 1.3107 1.3015 1.2924 100 1.2363 1.2865 I
12684 12815 200 1.2237 ~
12686 2.20 12067 12553 1.2492 2.40 1.1 12345 200 1.1743 1.1987 1
1.2155 2.00 1.1694 I
1.1897 1
11992 3.00 11630 I
11850 12074 11873 3.20 t=+/-i+/-
1.1790 1.1992 1.1726 3040 1.1743m 11629 3.00 1.1677 1.1674 3.90 1.1615 11384 4.00 1.1323 1.1550 1.1740 420 1.1337 11459 1.1587 1.1750 4.40 11352 1.1383 1.1532 11778 400 11350 11279 1.1461 11884 4.00 1.1347 1.1189 §u~
5.00 1.1330 1.1091 1.1299 12055 I
520 1.1294 1.1028 1.1321 12092 5.40 1.1255 10989 1.1350 12139 560 1.1247 10650 1.1389 12230 5.80 1.1319 1.0971 1.1524 1.2427 6.00 1.1381 1.1056 1.1856 12578 620 1.1438 1.1121 1.1787 12699 6.40 1.1481 11195 11901 12777 6.60 11500 11248 11977 1.2822 6.90 1.1522 11291 12045 12640 7.00 1.1530 1.1342 12085 1.2814 7.20 1.1524~
12097 12720 7.40 11557 1
12080 12830
'.00 11594
.2038 12485 700 1.1638 1.1856 11976 12327 800 11717 1.1742 1898 1.2155 820 1.1779 1.1791 1.1787 1.1924 8.40 1.1838
~
1.1670 11728 800 11879 1.1526 11577 8.80 11981 1.1411 11482 9.00 12056 11397 1.1356 9.20 12111 12417 I
1.1388 11533 9.40
.2114 12589 1.1370 11808 9.00 2160 12711 11599 12245 969 2195 1.2804 11952 12824 10.00 12236 1.2983 12254 1.2985 10.20 12276 12874 12585 13265 10040 12311 1.2887 1.2793 13519 10.00 1.2858 1.2991 1.3714 10.80
.2394 12873 1.3071 13687 11.00
.2494 1.2957 13958 1.4047 11.20 12436 13185 13027 13987 11.40 I
12473 13199 1.3047 13938 1160 1=
12496 13387 12869 13004 I
11.80 12549 1.3484 1,2746 1.3IlOO I
12.00 (core lop) 12763 1,3873 I
Note: W(Z) values at 20000 MWOIMTU may be applied to cycle bumups greater than 20000 MWDIMTU to prevent W(Z) function extrapolation
COLR BRAIDWOOD 2 Revision 4 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 Table 2.6.2.b Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup (MWD/MTU) 323 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 2 Revision 4 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE IS 2.7 Nuclear Enthalpy Rise Hot Channel FClctor (FN~ (LCO 3.2.2) 2.7.1 FN AH
~~P[1.0 + PFAH(1.0 - P)]
where: p:: the ratio of THERMAL POWER to RATED THERMAL POWER F~~P:: 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 FN AH shall be calculated by the following formula:
where:
UF,JHm:: Base FN AH measurement uncertainty::;: 1.04 2.7.3 PDMS Alarms:
FN r1H Warning Setpoint :: 2% of FNAH Margin FN
'1H Alarm Setpoint :: 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 1.536 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 2 Revision 4 Page 10 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 120 100 0::w ble 3=0 80 0..
...J
<:C
- Ie 0::
W 60
- l-ew I-
<:C 40 0::-
0
~
Cl 20 o 40 20 -10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 2 Revision 4 11 of! 3 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature 11T Setpoint Parameter Values 2.10.1 The Overtemperature 11T reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature I1T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/ OF.
2.10.3 The Overtemperature I1T reactor trip setpoint pressure coefficient K:, 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) p' shall be equal to 2235 psig.
2.10.6 The measured reactor vessel 11T leadllag time constant '1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel 6T leadllag time constant t2shall be equal to 3 sec.
2.10.8 The measured reactor vessel 11T lag time constant '3 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 '5 shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant '6 shall be less than or equal to 2 sec.
2.10.12 The f1 (111) "positive" breakpoint shall be +10% 111.
2.10.13 The f1 (111) "negative" breakpoint shall be -18% 111.
2.10.14 The f1 (111) "positive" slope shall be +3.47% / % 111.
2.10.15 The f1 (111) "negative" slope shall be -2.61 % / % 111.
COLR BRAIDWOOD 2 Revision 4 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 15 2.11 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overpower ~T Setpoint Parameter Values 2.11.1 The Overpower ~T reactor trip setpoint ~ shall be equal to 1.072.
2.11.2 The Overpower LlT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02/ of for increasing Tavg 2.11.3 The Overpower LlT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to o/ of for decreasing Tavg 2.11.4 The Overpower LlT reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0.00245/ of when T 1".
2.11.5 The Overpower LlT reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0/ of when T 1".
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 LlT lead/lag time constant "(1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel LlT lead/lag time constant "(2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel LlT lag time constant "(3 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 (LlI) "positive" breakpoint shall be 0 for all Lll.
2.11.13 The f2 (LlI) "negative" breakpoint shall be 0 for all Lll.
2.11.14 The f2 (~I) "positive" slope shall be 0 for all Lll.
2.11.15 The f2 (LlI) "negative" slope shall be 0 for all Lli.
COLR BRAIDWOOD 2 Revision 4 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 (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 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 1682 2.13.2 a) prior to initial criticality 1730 2.13.2 b) all other times in life 1968