CPSES-200201029, Cycle 7 Core Operating Limits Report
| ML021070726 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/09/2002 |
| From: | Terry C TXU Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CPSES-200201029, TXX-02071 | |
| Download: ML021070726 (22) | |
Text
t TXU TXU Energy Comanche Peak Steam Electric Station P.O. Box 1002 (E01)
Glen Rose, TX 76043 Tel: 254 897 8920 Fax: 254 897 6652 lance.terry@txu.com C. Lance Terry Senior Vice President &
Principal Nuclear Officer Ref: 10CFR50.36 CPSES-200201029 Log # TXX-02071 File # 10010, 916(COLR), RN-48 April 9, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-446 THE UNIT 2, CYCLE 7 CORE OPERATING LIMITS REPORT Gentlemen:
Enclosed is the Core Operating Limits Report for Unit 2, Cycle 7 prepared and submitted pursuant to Technical Specification 5.6.5.
ITcc0e Cl A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak Diablo Canyon Palo Verde
° South Texas Project Wolf Creek
A TXU TXX-02071 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.
Sincerely, TXU By:
Generation Company LP TXU Generation Management Company LLC, Its General Partner C. L. Terry Senior Vice President and Principal Nuclear Officer By:
Roger D. Walker Regulatory Affairs Manager JDS/js Enclosures c -
E. W. Merschoff, Region IV W. D. Johnson, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES
ERX-02-002, Revision 0 CPSES UNIT 2 CYCLE 7 CORE OPERATING LIMITS REPORT April 2002 Prepared:
D
\\
nathan M. Ralston
- .Ractor Physics Reviewed:
f/
o, D
- lohn T. Bosma Reactor Physics Reviewed:
D Safety Analysis Approved:
M D
Stephen M. Maier Reactor Physics Supervisor Approved:
D Whee G. Choe Safety Analysis Manager ate:
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DISCLAIMER The information contained in this report was prepared for the specific requirement of TXU Energy and may not be appropriate for use in situations other than those for which it was specifically prepared.
TXU Energy PROVIDES NO WARRANTY HEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE.
By making this report available, TXU Energy does not authorize its use by others, and any such use is forbidden except with the prior written approval of TXU Energy.
Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein.
In no event shall TXU Energy have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this report or of the information in it.
ii
COLR for CPSES Unit 2 Cycle 7 TABLE OF CONTENTS DISCLAIMER ii TABLE OF CONTENTS iii LIST OF FIGURES iv SECTION PAGE 1.0 CORE OPERATING LIMITS REPORT........................................
1 2.0 OPERATING LIMITS....................................................
2 2.1 SAFETY LIMITS 2
2.2 SHUTDOWN MARGIN 2
2.3 MODERATOR TEMPERATURE COEFFICIENT 2
2.4 ROD GROUP ALIGNMENT LIMITS 3
2.5 SHUTDOWN BANK INSERTION LIMITS 3
2.6 CONTROL BANK INSERTION LIMITS 4
2.7 PHYSICS TESTS EXCEPTIONS - MODE 2 4
2.8 HEAT FLUX HOT CHANNEL FACTOR 4
2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 5
2.10 AXIAL FLUX DIFFERENCE 6
2.11 REACTOR TRIP SYSTEM INSTRUMENTATION 6
2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS 7
2.13 BORON CONCENTRATION 8
3.0 REFERENCES
8 iii
COLR for CPSES Unit 2 Cycle 7 LIST OF FIGURES FIGURE PAGE 1
REACTOR CORE SAFETY LIMITS.........................................
9 2
ROD BANK INSERTION LIMITS VERSUS THERMAL POWER.....................
10 3
K(Z)
- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT.......................................................
11 4
W(Z) AS A FUNCTION OF CORE HEIGHT (MAXIMUM) 12 5
W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 13 6
W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 14 7
W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 15 8
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER.............................................
16 iv
COLR for CPSES Unit 2 Cycle 7 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPSES UNIT 2 CYCLE 7 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Specifications affected by this report are listed below:
SL 2.1 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 3.3.1 LCO 3.4.1 LCO 3.9.1 SAFETY LIMITS SHUTDOWN MARGIN MODERATOR TEMPERATURE COEFFICIENT ROD GROUP ALIGNMENT LIMITS SHUTDOWN BANK INSERTION LIMITS CONTROL BANK INSERTION LIMITS PHYSICS TESTS EXCEPTIONS - MODE 2 HEAT FLUX HOT CHANNEL FACTOR NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR AXIAL FLUX DIFFERENCE REACTOR TRIP SYSTEM INSTRUMENTATION RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS BORON CONCENTRATION 1
COLR for CPSES Unit 2 Cycle 7 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 have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5b, Items 5 and 9 through 19, as supplemented by Item 20.
These limits have been determined such that all applicable limits of the safety analysis are met.
2.1 SAFETY LIMITS (SL 2.1) 2.1.1 In MODES 1 and 2, the combination of thermal power, reactor coolant system highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 1.
2.2 SHUTDOWN MARGIN (SDM)
(LCO 3.1.1) 2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 with Keff < 1.0, and in MODES 3, 4, and 5.
2.3 MODERATOR TEMPERATURE COEFFICIENT (MTC)
(LCO 3.1.3) 2.3.1 The MTC upper and lower limits, respectively, are:
The BOL/ARO/HZP-MTC shall be less positive than +5 pcm/ 0F.
The EOL/ARO/RTP-MTC shall be less negative than -40 pcm/ 0F.
2
COLR for CPSES Unit 2 Cycle 7 2.3.2 SR 3.1.3.2 The MTC surveillance limit is:
The 300 ppm/ARO/RTP-MTC shall be less negativ(
than or equal to -31 pcm/ 0F.
The 60 ppm/ARO/RTP-MTC shall be less negative than or equal to -38 pcm/ 0F.
where:
BOL stands for Beginning of Cycle ARO stands for All Rods Out HZP stands for Hot Zero THERMAL PO0 EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER Li f*
WER 2.4 ROD GROUP ALIGNMENT LIMITS (LCO 3.1.4) 2.4.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODES 1 and 2.
2.5 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.5) 2.5.1 The shutdown rods shall be fully withdrawn.
Fully withdrawn shall be the condition where shutdown rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.
3 e
e
COLR for CPSES Unit 2 Cycle 7 2.6 CONTROL BANK INSERTION LIMITS (LCO 3.1.6) 2.6.1 The control banks shall be limited in physical insertion as shown in Figure 2.
2.6.2 The control banks shall always be withdrawn and inserted in the prescribed sequence.
For withdrawal, the sequence is control bank A, control bank B, control bank C, and control bank D.
The insertion sequence is the reverse of the withdrawal sequence.
2.6.3 A 115 step Tip-to-Tip relationship between each sequential control bank shall be maintained.
2.7 PHYSICS TESTS EXCEPTIONS - MODE 2 (LCO 3.1.8) 2.7.1 The SDM shall be greater than or equal to 1.3% ak/k in MODE 2 during PHYSICS TESTS.
2.8 HEAT FLUX HOT CHANNEL FACTOR (FQ(Z))
FQRTP 2.8.1 FQ(Z)
[K(Z)] for P
FQ (Z)
FQRTP 0.5 (LCO 3.2.1)
"P > 0.5
[K(Z)] for P
- 0.5 where:
P =
THERMAL POWER RATED THERMAL POWER 4
COLR for CPSES Unit 2 Cycle 7 2.8.2 FQRTP = 2.42 2.8.3 K(Z) is provided in Figure 3.
2.8.4 Maximum elevation dependent W(Z) values are given in Figure 4.
Figures 5, 6, and 7 give burnup dependent values for WMZ).
Figures 5, 6, and 7 can be used in place of Figure 4 to interpolate or extrapolate (via a three point fit) the W(Z) at a particular burnup.
2.8.5 SR 3.2.1.2 If the two most recent FQ(Z) evaluations show an increase in the expression maximum over Z
[ FQC(Z)
/ K(Z) ]
FQw(Z) shall be increased by a factor of 1.02.
This requirement is for all cycle burnups.
2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FTMAH.
(LCO 3.2.2) 2.9.1 FNAH FRTPAH [1 + PFAH (l-P)]
where:
P =
THERMAL POWER RATED THERMAL POWER 2.9.2 FRT*PAH =
1.55 2.9.3 PFAH
= 0.3 5
COLR for CPSES Unit 2 Cycle 7 2.10 AXIAL FLUX DIFFERENCE (AFD)
(LCO 3.2.3) 2.10.1 The AFD target band is
+5%,
-12% at 100% RTP linearly expanding to
+20%,
-17% at 50% RTP.
Below 50% RTP, the AFD target band remains constant at +20%,
-17%.
2.10.2 The AFD Acceptable Operation Limits are provided in Figure 8.
2.11 REACTOR TRIP SYSTEM (RTS)
INSTRUMENTATION (LCO 3.3.1) 2.11.1 The numerical values pertaining to the Overtemperature N-16 reactor trip setpoint are listed below:
K1 K2 K3 TcP pI T,
T2
= 1.150
= 0.0145 /PF
= 0.00075 /psig
=
560.5 'F
> 2235 psig 10 sec
_ 3 sec f1(Aq)
=
0.00
{(qt-qb) + 65%}
=
0%
2.03- {(qt-qb) - 7.3%}
when (qt-qb) < -65% RTP when -65% RTP < (qt-qb)
< +7.3% RTP when (qt-qb) > +7.3% RTP 6
COLR for CPSES Unit 2 Cycle 7 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB)
LIMITS (LCO 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the surveillance limits specified below:
2.12.2 SR 3.4.1.1 Pressurizer pressure
Ž 2220 psig 2 2222 psig (4 channels)
(3 channels)
The pressurizer pressure limits correspond to the analytical limit of 2205 psig used in the safety analysis with allowance for measurement uncertainty.
These uncertainties are based on the use of control board indications and the number of available channels.
2.12.3 SR 3.4.1.2 RCS average temperature g
592 OF 592 OF (4 channels)
(3 channels)
The RCS average temperature limits correspond to the analytical limit of 595.7 OF used in the safety analysis with allowance for measurement uncertainty.
These uncertainties are based on the use of control board indications and the number of available channels.
7
COLR for CPSES Unit 2 Cycle 7 2.12.4 SR 3.4.1.3 The RCS total flow rate based on precision heat balance shall be ; 408,000 gpm 2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be Ž 408,000 gpm The required RCS flow, based on an elbow tap differential pressure instrument measurement prior to MODE 1 after the refueling outage, shall be greater than 317,000 gpm.
2.13 BORON CONCENTRATION (LCO 3.9.1) 2.13.1 The required refueling boron concentration is 2225 ppm.
3.0 REFERENCES
Technical Specification 5.6.5.
8
COLR for CPSES Unit 2 Cycle 7 FIGURE 1 REACTOR CORE SAFETY LIMITS 670 660 6
UNACCEPTABLE P = 2385 psig OPERATION 650 P
P2235 psig 640 630 620 L L P
1 4 s
0 610 560 550 0
20 40 60 80 100 120 PERCENT OF RATED THERMAL POWER 9
COLR for CPSES Unit 2 Cycle 7 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 0
10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER NOTES:
- 1.
Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.
- 2.
Control Bank A shall be fully withdrawn.
10 240 220 200
-- 180 160 (J}
CL 140 z
0 120 U) 0 100 z
80 0
0 n,60 40 20 0
(25.3,218)
(79.6.218)
(10...64 )
1 i
- J ii
- !i I
- ~
~
~
BN BAKBC!!
i' i L K !
It (100,146)
- I i
t
]
F _-
D1_
-NC_
-1t_
___3_10)
COLR for CPSES Unit 2 Cycle 7 FIGURE 3 K(Z)
NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8 N
I.* 0.7 w
N o.6 X:
0.5 0
z 0.4 N
0.3 0.2 0.1 0.0 1
2 3
4 5
6 7
8 9
10 11 12 CORE HEIGHT (FEET)
TOP K(Z) 0.9250 0.9275 0.9300 0.9325 0.9350 0.9375 0.9400 0.9425 Axial Node 53 52 51 50 49 48 47 46 K(Z) 0.9450 0.9475 0.9500 0.9525 0.9550 0.9575 0.9600 0.9625 Axi al Node 45 44 43 42 41 40 39 38 K(Z) 0.9650 0.9675 0.9700 0.9725 0.9750 0.9775 0.9800 0.9825 Axial Node 37 36 35 34 33 32 1 - 31 K(Z) 0.9850 0.9875 0.9900 0.9925 0.9950 0.9975 1.0000 0
BOTTOM Axial Node 61 60 59 58 57 56 55 54 Core Height (ft) = (Node - 1)
- 0.2 11 (0.0,1 0)
(6.0,1.0,
'i (12.0,10.925) 17IT II TI F 7T,i Il 1 IT I
I 1i~
i S!
i --
-i i
I
-l
! !~
i, * [
i-,-
COLR for CPSES Unit 2 Cycle 7 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (MAXIMUM) 0 1
2 3
4 5
6 7
8 9
10 11 12 BOTTOM CORE HEIGHT (FEET)
TOP Axial Node 41 40 39 38 37 36 35 34 33 32 31 W(Z) 1.131 1.131 1.130 1.129 1.126 1.123 1.119 1.112 1.105 1.105 1.108 Axial Node 30 29 28 27 26 25 24 23 22 21 20 W(Z) 1.117 1.125 1.131 1.136 1.141 1.145 1.148 1.149 1.150 1.151 1.150 Axial Node 19 18 17 16 15 14 13 12 11 1 - 10 W(Z) 1.149 1.154 1.158 1.162 1.171 1.182 1.191 1.200 1.209 Core Height (ft) = (Node - 1)
- 0.2 12 1.300 1.250 1.200 N
1.150 1.100 1.050 1.000 Axial Node 52 - 61 51 1
50 1
49 1
48 1
47 1
46 1
45 1
44 1
43 1
42 1
W(Z)
.130
.135
.135
.130
.126
.127
.129
.130
.130
.130
COLR for CPSES Unit 2 Cycle 7 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.300 I
1.250 I
- i jIiz
__i 1.200 i
If i
I I
I 1
iii
- )1.150 I
I I
1.100 i
i-I 1.050 I
I,
-i I
ii 1.000
-I-0 1
2 3
4 5
6 7
8 9
10 11 12 BOTTOM CORE HEIGHT (FEET)
TOP Axial Node W(Z) 52 - 61 51 1.119 50 1.111 49 1.107 48 1.107 47 1.108 46 1.110 45 1.111 44 1.112 43 1.113 42 1.113 Axial Node W(Z) 41 1.112 40 1.110 39 1.108 38 1.106 37 1.103 36 1.101 35 1.100 34 1.100 33 1.102 32 1.105 31 1.107 Axial Node W(Z) 30 1.110 29 1.114 28 1.118 27 1.122 26 1.126 25 1.129 24 1.133 23 1.137 22 1.140 21 1.142 20 1.145 Axial Node W(Z) 19 1.149 18 1.154 17 1.158 16 1.162 15 1.166 14 1.170 13 1.173 12 1.176 11 1.179 1 - 10 Core Height (ft) = (Node - 1)
- 0.2 13
COLR for CPSES Unit 2 Cycle 7 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU) 1.300 J
1.250 SI i
1.200 I
I
- 1.150 Ii 1.100 i
i i
K i
'i I
FF mm _:
zii
~1.050 1.100 7
iI 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM CORE HEIGHT (FEET)
TOP Axial Node W(Z) 52 - 61 51 1.122 50 1.114 49 1.110 48 1.109 47 1.109 46 1.111 45 1.113 44 1.114 43 1.115 42 1.115 Axial Node W(Z) 41 1.115 40 1.113 39 1.111 38 1.109 37 1.105 36 1.101 35 1.098 34 1.095 33 1.094 32 1.096 31 1.101 Axial Node W(Z) 30 1.108 29 1.112 28 1.116 27 1.120 26 1.125 25 1.130 24 1.134 23 1.136 22 1.138 21 1.140 20 1.142 Axial Node W(Z) 19 1.144 18 1.147 17 1.153 16 1.161 15 1.171 14 1.179 13 1.187 12 1.194 11 1.199 1 - 10 Core Height (ft) = (Node - 1)
- 0.2 14
COLR for CPSES Unit 2 Cycle 7 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 0 1
2 3
4 5
6 7
8 9
10 11 12 CORE HEIGHT (FEET)
Axial Node W(Z) 52 - 61 51 1.130 50 1.135 49 1.135 48 1.130 47 1.126 46 1.127 45 1.129 44 1.130 43 1.130 42 1.130 Axial Node W(Z) 41 1.131 40 1.131 39 1.130 38 1.129 37 1.126 36 1.123 35 1.119 34 1.112 33 1.105 32 1.103 31 1.108 Axial Node W(Z) 30 1.117 29 1.125 28 1.131 27 1.136 26 1.141 25 1.145 24 1.148 23 1.149 22 1.150 21 1.151 20 1.150 Axial Node W(Z) 19 1.148 18 1.146 17 1.149 16 1.159 15 1.171 14 1.182 13 1.191 12 1.200 11 1.209 1 - 10 Core Height (ft) = (Node - 1)
- 0.2 15 1.300 1.250 1.200 D 1.150 1.100 1.050 1.000
_I I
i l
i i
I i
i i
1 i
i
- T BOTTOM TOP
COLR for CPSES Unit 2 Cycle 7 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER
-30
-20
-10 0
10 20 DEVIATION FROM TARGET AXIAL FLUX DIFFERENCE (%)
30 16 100 90 80 S!
I,
'j7 7
TiI!
(-15,90)
I (11 90) i i
F Ii SUNACCEPTABLE F
UNACCEPTABLE
_UACETACCEPTABLEBLE I
I OPERATION
'I ii I F
i FI i
i*
1j i..
I I
(-26,50)
(2, I,
' i i
t
[
I
- ' I I
(29,50)
F F
F F
- I F
I t i
i ff: i F
i
-4 Si
, 2 :
i
-44 i~~~
-T-77T-I I
L 7rl ý
! ii
- ___1, 70 60 50 40 30 w
0 0
a 0:_
w I
w w
I (U
Iz 0
LU 0.
20 10 0
-40 40