NL-08-1664, Cycle 20 Core Operating Limits Report
| ML083020482 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/27/2008 |
| From: | Ajluni M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-08-1664 | |
| Download: ML083020482 (16) | |
Text
Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205992.5000 October 27, 2008 SOUTHERN'\\
COMPANY Energy to Serve Your WorLdS" Docket No.:
50-364 NL-08-1664 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 20 Core Operating Limits Report Ladies and Gentlemen:
In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) for Joseph M. Farley Nuclear Plant Unit 2 Cycle 20, Rev. O.
This letter contains no NRC commitments. If there are any questions, please advise.
Sincerely,
~~~
M. J. Ajluni Manager, Nuclear Licensing MJAlSYAldaj
Enclosure:
FNP Core Operating Limits Report Unit 2 - Cycle 20, Rev. 0 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054: LC# 14852 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. K. D. Feintuch, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 2 Cycle 20 Core Operating LImits Report Enclosure FNP Core Operating Limits Report Unit 2-Cycle 20, Rev. 0
SOUTHERNA COMPANY EMrgy toServe }'ourWorltr Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 20 Revision 0
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 1 of 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 18 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Requirement affected by this report is listed below:
13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 (with kef! ~1)
The Technical Specifications affected by this report are listed below:
2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with keff < 1), 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor _ FQ(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor _ F~
3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature LlT (OTLlT) and Overpower LlT (OPLlT) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration
COlR for FNP Unit 2 Cycle 20 Revision 0 Page 2 of 13 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 NRC approved methodologies, including those specified in Technical Specification 5.6.5.
2.1 SHUTDOWN MARGIN - MODES 1 AND 2 (with k..ff ~1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent L\\k1k.
2.2 SHUTDOWN MARGIN - MODES 2 (with k..ff < 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keft < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent L\\k1k.
2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent L\\k1k.
2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOUARO/HZP-MTC shall be less than or equal to +0.7 x 10-4 L\\k1k1°F for power levels up to 70 percent RTP with a linear ramp to 0 L\\k1k1°F at 100 percent RTP.
The EOUARO/RTP-MTC shall be less negative than -4.3 x 10-4 L\\k1k1°F.
2.3.2 The MTC Surveillance limits are:
The 300 ppm/ARO/RTP-MTC should be less negative than or equal to
-3.65 x 10-4 L\\kIk!°F.
The 100 ppm/ARO/RTP-MTC should be less negative than
-4.0 x 10-4 L\\k1k1°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 RTP stands for RATED THERMAL POWER
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 3 of 13 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.
2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.
2.6 Heat Flux Hot Channel Factor - Fo{Z) (Specification 3.2.1)
F,RTP 2.6.1 Fo{Z) ~ _0- *K{Z) for P > 0.5 P
F,RTP Fo{Z) ~ _0- *K{Z) for P ~ 0.5
0.5 where
P =
THERMAL POWER RATEDTHERMAL POWER FtTP 2.6.2
=2.50 2.6.3 K{Z) is provided in Figure 2.
TP 2.6.4 Fo{Z) ~ Ft *K{Z) for P > 0.5 P*W{Z) 2.6.5 W{Z) values are provided in Table 4.
2.6.6 The Fo{Z) penalty factors are provided in Table 1.
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 4 of 13 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F:f., (Specification 3.2.2)
P =
THERMAL POWER where:
RA TED THERMAL POWER 2.72 F1it = 1.70 2.7.3 PF~ =0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.
2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm. 1 2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 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 safety limits specified in Figure 4.
2.11 Reactor Trip System Instrumentation Overtemperature ~T (OT~nand Overpower ~T (Op~n Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower ~T (OP~T) setpoint parameter values for TS Table 3.3.1 1 are listed in COLR Tables 2 and 3.
This concentration bounds the condition of keffS 0.95 (all rods in less the most reactive rod) and subcriticality (§ll rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 5 of 13 2.12 RCS ONB Parameters for Pressurizer Pressure. RCS Average Temperature. and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS ONB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:
- a. Pressurizer pressure ~ 2209 psig;
- b. RCS average temperature :5 580.3°F; and
- c. The minimum RCS total flow rate shall be ~ 263,400 GPM when using the precision heat balance method and ~ 264.200 GPM when using the elbow tap method.
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 6 of 13 Table 1 FQ(Z) Penalty Factor Cycle FQ(Z)
Burnup Penalty (MWDIMTU)
Factor 4439 1.020 4643 1.026 4847 1.031 5051 1.030 5255 1.028 5460 1.026 5664 1.024 5868 1.023 6072 1.020 Notes:
- 1. The Penalty Factor, to be applied to Fa{Z) in accordance with SR 3.2.1.2, is the maximum factor by which Fa{Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting from the burnup at which the Fa{Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle burnups.
- 3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 7 of 13 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAn Setpoint Parameter Values pi =2235 psig K2 =0.017/oF K3 =0.000825/psi
'tl ~ 30 sec
't2 ~ 4 sec
't4= 0 sec
't5~ 6 sec
't6~ 6 sec
-2.48 {23 + (qt qb)}
when (qt qb) ~ -23% RTP 0% ofRTP when -23% RTP < (qt -qb) ~ 15% RTP 2.05 {(qt - qb) 15}
when (qt qb) > 15% RTP
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 8 of 13 Table 3 Reactor Trip System Instrumentation* Overpower AT (OPAT)
Setpoint Parameter Values
~= 1.10 Ks =0.02/°F for increasing Tavg Ks =0.00109/°F when T > T" Ks = O/oF for decreasing Tavg Ks =O/oF when T:s; T"
't3~ 10 sec
't4= 0 sec
'ts:S; 6 sec
't6:S; 6 sec f2(~I) =0% RTP for all ~I
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 9 of 13 Table 4 RAOCW(Z}
AxiaJ Point Elevation (feet) 150 MWDIMTU 3000 MWDIMTU 10000 MWDIMTU 18000 MWDIMTU 1
12.00 1.0000 1.0000 1.0000 1.0000 2
H.80 1.0000 1.0000 1.0000 1.0000 3
1l.60 1.0000 1.0000 1.0000 1.0000 4
11.40 1.0000 1.0000 1.0000 1.0000 5
1l.Z0 1.0000 1.0000 1.0000 1.0000 6
U.OO 1.1925 l.Z661 l.Z403 l.Z498 7
10.80 1.1910 1.2583 l.Z384 1.2422 8
10.60 1.1862 1.2480 1.2347 1.2349 9
10.40 1.1820 1.2375 1.2310 l.Z277 10 10.20 1.1797 1.2261 l.Z284 l.Z203 H
10.00 1.1829 1.2136 1.2245 1.2126 12 9.80 1.1856 1.2045 1.2194 l.Z052 13 9.60 1.1842 1.1966 1.2134 l.l959 14 9.40 l.l812 1.1897 1.2065 l.l910 IS 9.20 l.l787 1.1857 l.l987 l.l982 16 9.00 1.1718 l.l772 l.l888 1.2218 17 8.80 1.1730 1.1782 l.l967 1.2445 18 8.60 l.l836 l.l884 I.2IGS 1.2662 19 8.40 1.1955 1.1980 1.2244 1.2913 20 8.20 1.2042 1.2049 1.2352 1.3130 21 8.00 1.2104 1.2094 1.2434 1.3309 21 7.80 1.2143 1.2U6 1.2489 1.3449 23 7.60 1.2157 1.2U3 1.2517 1.3550 24 7.40 1.2151 1.2093 1.2520 1.3614 25 7.20 1.2138 1.2065 1.2499 1.3640 26 7.00 1.2106 1.2020 1.2471 1.3631 27 6.80 1.2055 l.l957 1.2425 1.3589 28 6.60 1.1988 l.l880 1.2358 1.3517 29 6.40 1.1908 1.1789 1.2273 1.3415 30 6.20 1.1815 1.1687 1.2171 1.3288 31 6.00 1.1712 1.1577 1.2057 1.3133 32 5.80 1.1594 1.1449 l.l916 1.2962 33 5.60 1.1480 1.1341 l.lSOO l.Z748 34 5.40 1.1545 l.l357 l.l763 1.2540 35 5.20 l.l645 l.l432 l.l757 1.2491 36 5.00 l.l740 l.lS03 1.1740 1.2462 37 4.80 1.1829 1.1566 l.l7l0 1.2406 38 4.60 1.1908 l.l621 l.l668 l.Z332 39 4.40 1.1978 l.l666 1.1614 1.2136 40 4.20 1.2036 1.1703 l.l547 1.2U8 41 4.00 1.2082 1.1729 l.l483 1.1982 42 3.80 1.2U7 1.1747 1.1436 l.l824 43 3.60 1.2140 1.1752 l.l427 1.1677 44 3.40 1.2152 1.1751 1.1399 l.l563 45 3.20 1.2165 1.1798 1.1372 l.l445 46 3.00 1.2201 1.1930 1.1352 l.l441 47 2.80 1.2312 1.2137 l.l373 U57l 48 2.60 1.2523 1.2377 l.l477 1.1753 49 2.40 1.2780 1.2610 l.l572 1.1920 SO 2.20 1.3036 l.Z841 1.1669 1.2084 51 2.00 1.3287 1.3067 1.1767 1.2247 52 1.80 1.3531 1.3286 1.1864 1.2408 53 1.60 1.3766 1.3496 l.l962 1.2567 54 1.40 1.3989 1.3694 1.2060 1.2725 55 1.20 1.4197 1.3876 1.2156 1.2880 56 1.00 1.4386 1.4040 1.2247 1.3030 57 0.80 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1.0000 1.0000 Top and bottom 5 axial points excluded per Technical Specification B 3.2.1.
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 10 of 13 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 200 175 I 150 i
'C l1. 125
~
c
- eo 100
~
Do
~
C III III "8
75 a:
50 25 o
0.0 0.1 I
I I
I I
I
~
(.552,225)
(1, 187) _
~
Banke
~
(0. 114)
BankO
~
(.070,0)
I I I I I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of RATED THERMAL POWER Fully Withdrawn shall be the condition where control rods are at a position within the interval :it 225 and ~ 231 steps withdrawn.
Note: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 128 steps.
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 11 of 13 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1
0 13 0.8 ca LL Q
C
~
ca Q)
D..
"g 0.6 Q)
.~
"iii E 0 z
- NO.4
- t:
0.2 Core Height (ft.)
K(Z) 0.000 1.000 6.000 1.000 12.000 1.000 Fa = 2.50 o
o 2
4 6
8 10 12 Core Height (feet)
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 12 of 13 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOe 120 110 100 90
~
w
~
80 0
l1.
..I c( 70
~ a:
w
- J:
I 60 Q w S 50
'0
~...
40
(-12.100)
(+9,100)
I-UNACCEPTABLE V
\\
UNACCEPTABLE
- j
\\
OPERATION -
OPERATION J
ACCEPTABLE \\
I OPERATION,
J I
\\
(-30,50)
(+24.50)
Gl J 0
l1.
30 20 10 o
-60
-SO
-40
-30
-20
-10 o
10 20 30 40 50 60 Axial Flux Difference (Delta I) %
COLR for FNP Unit 2 Cycle 20 Revision 0 Page 13 of 13 Figure 4 Reactor Core Safety Limits 680 660 640
--<>-2425 psig I
UNACCEPTABLE I 0...
I OPERATION I
......... to-...
................. r--....
- 10.
.............. r---..
r---... r---...
r---... j'....
r"""-........
................. ~
r"""-.........
......... r--.. i'--..
""0 r---...
r---...
r\\
Ix..
\\
r--....
to-...
r-...
I'--
\\
r---
...... I'--
r'.
)
i'--..
r-.....
......... I'--
....... I'--.......
I"--I'--
......... I'--.
r---...
ACCEPTABLE
........ r--....
OPERATION
~
~2235psig
~1985pslg
-X-1825 psig 600 580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)