NL-09-0302, Cycle 23 Core Operating Limits Report
| ML091070071 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/15/2009 |
| From: | Ajluni M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-09-0302 | |
| Download: ML091070071 (15) | |
Text
Southern Nuclear Operating Company, inc.
April 15, 2009 SOUTHERN'\\
COMPANY Energy to Sen-e YOUI' WorLd Docket No.:
50-348 NL-09-0302 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Unit 1 Cycle 23 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 1 Cycle 23, Rev. O.
This letter contains no NRC commitments. If there are any questions, please advise.
Sincerely,
~9T M. J. Ajluni Manager, Nuclear Licensing MJAlSYAldaj
Enclosure:
FNP Core Operating Limits Report Unit 1 - Cycle 23, Rev. 0 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Ms. P. M. Marino, Vice President - Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant Unit 1 Cycle 23 Core Operating Limits Report Enclosure FNP Core Operating Limits Report Unit 1
- Cycle 23, Rev. 0
SOUTHERN A COMPANY Energy to Serve Your World" Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 23 Revision 0
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 23 MARCH 2009 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT I CYCLE 23 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 I and 2 (with kcff~ I)
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 kcff< 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 Overtempemture ~T (OT~T) and Overpower ~T (OP~T) Setpoint Parameter Values for Table 3.3.1-1 3.4. I RCS DNB Pammeters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration Page I of 12
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23 MARCH 2009 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 keff> 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent &/k.
2.2 SHUmOWN MARGIN - MODES 2 (with keff< 1.0),3,4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keD- < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent &/k.
2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent &/k.
2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOLIARO-MTC shall be less than or equal to +0.7 x 10-4 ~k!kJ°F for power levels up to 70 percent RTP with a linear ramp to 0 ~oF at 100 percent RTP.
The EOLIAROIRTP-MTC shall be less negative than -4.3 x 10-4 ~k!kJ°F.
2.3.2 The MTC Surveillance limits are:
The 300 ppmJAROIRTP-MTC should be less negative than or equal to
-3.65 x 10-4 ~k!krF.
The 100 ppmJAROIRTP-MTC should be less negative than -4.0 x 10-4 ~k!k!°F.
where: BOL stands for Beginning ofCycle Life ARO stands for All Rods Out EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 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.
Page 2 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23 MARCH 2009 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 - FQ(Z) (Specification 3.2.1) forP > 0.5 for P ~ 0.5 where:
P =
THERMAL POWER RATED THERMAL POWER 2.6.2 F;TP =2.50 2.6.3 2.6.4 K(Z) is provided in Figure 2.
F RTP *K(Z)
F (Z) < ---,,-Q--
Q P*W(Z)
F RTP *K(Z)
F (Z)<----:o...Q--
Q 0.5* W(Z) for P > 0.5 forP ~ 0.5 2.6.5 2.6.6 W(Z) values are provided in Table 4.
The FQ(Z) penalty factors are provided in Table 1.
Page 3 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 23 MARCH 2009 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F}; (Specification 3.2.2)
P =
THERMAL POWER where:
RATED THERMAL POWER 2.7.2 F::P = 1.70 2.7.3 PFMf = 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial FluJSpifference (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. l 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~Tl and Ovemower ~T (OP~T)
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.
2.12 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:
- a. Pressurizer pressure 2': 2209 psig;
- b. RCS average temperature :c:; 580.3°F; and
- c. The minimum RCS total flow rate shall be 2': 263,400 GPM when using the precision heat balance method and 2': 264,200 GPM when using the elbow tap method.
This concentration bounds the condition of""tr:C:; 0.95 (all rods in less the most reactive rod) and subcriticality (ill! rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.
Page 4 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23 MARCH 2009 Table 1 FQ{Z) Penalty Factor Cycle FQ(Z)
Burnup Penalty (MWDIMTU)
Factor 30 1.027 150 1.027 354 1.033 558 1.036 763 1.037 967 1.034 1171 1.029 1375 1.023 1580 1.020 Notes:
- 1. The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ(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 bumup at which the FQ(Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle bumups.
- 3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.
Page 5 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23 MARCH 2009 Table 2 Reactor Trip System Instrumentation - Overtemperature !\\T (OTt\\.T)
Setpoint Parameter Values P' =2235 psig Kl = 1.17 K3 = 0.000825jpsi tl ~ 30 sec
't'2~ 4 sec t'4= 0 sec t'5~ 6 sec h(M) =
-2.48 {23 + (ql - qb)}
when (qt - qb) ~ -23% RTP 0% ofRTP when -23% RTP < (qt -qb) ~ 15% RTP 2.05 {(ql - qb) -IS}
when (ql - qb) > 15% RTF Page 6 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 23 MARCH 2009 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)
Setpoint Parameter Values I<.4 = 1.10 Ks =O.02rF for increasing Tavg K6 = O.OO109rF when T> T" Ks = OrF for decreasing Tavg K6== OrF when T ~ Til
't3~ 10 sec
't4= 0 sec
't5~ 6 sec
't6~ 6 sec fz(M) = 0% RTP for all M Page 7 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23 MARCH 2009 Table 4 RAOCW(Z)
I I
i Axial PoInt I
2 3
4 5
6 7
8 9
10 II 12 13 14 IS 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 SO 51 52 53 54 55 56 57 58 59 60 61 Elevation (feet) lZ.OO 11.841 11.641 11.46 1\\.20 11.00 lo.s0 10.60 lOAD 10.20 10.00 UO 9.60 9040 9.20 9.00 8.80 8.60 8.40 8.20 8.00 7.8ll 7.60 7.40 7.20 7.00 6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4040 4.20 4.00 3.8ll 3.60 3.40 3.20 3.00 2.8ll 2.60 2040 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00
]SOMWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 l.2003 1.1959 1.1889 1.1819 1.1741 1.1652 1.1640 1.1657 t.l641 1.161\\
1.1559 t.l5!O 1.1624 1.1741 1.1824 1.1885 1.1925 1.1942 t.l942 1.1934 1.1911 1.1871 1.1817 1.1751 1.1673 1.151lO 1.1479 1.1430 1.1503 1.1588 t.t664 t.l735 t.l795 t.t849 1.1919 1.1988 1.2047 1.2093 1.21341 1.2179 1.2237 1.2400 1.2663 1.21lO3 1.3143 1.3379 1.3607 1.3826 1.4034 1.4228 1.4403 1.0000 1.0000 1.0000 1.0000 1.0000 3000 MWD/MTU t.OOOO 1.0000 1.0000 1.0000 1.0000 1.2659 1.2591 1.2497 1.2395 1.2283 1.2164 1.2038 1.1930 1.1871 1.1781 1.1688 1.1789 1.1812 1.1907 1.1976 1.2020 1.2041 1.2040 1.2019 1.1979 1.1922 1.1849 1.1763 1.1665 1.1556 1.1437 1.1326 1.1298 1.1388 1.1458 1.1519 1.1576 1.1612 1.]661 1.1691 1.1704 1.1739 1.1793 1.1836 1.11lO3 1.1981 1.2123 1.2319 1.2504 1.2730 1.2961 1.3181 1.3392 1.3592 1.3775 1.3940 1.0000 1.0000 1.0000 1.0000 1.0000
]0000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 l.2557 1.2533 1.2511 1.2489 1.2416 1.2295 1.2274 1.2287 1.2264 1.2227 1.2129 1.2331 1.1477 1.2593 l.2680 1.2736 1.2763 1.2761 1.2731 1.2676 l.2598 1.2498 1.2380 1.2244 1.2094 1.1956 1.1831 1.1713 1.1653 1.1656 1.1656 1.1638 1.1612 t.lS73 1.1524 1.1465 1.1417 1.1376 1.1325 1.1287 1.1256 1.1263 1.1328 1.1426 1.1512 1.1617 1.1714 1.1810 1.1905 1.1998 1.2085 1.0000 1.0000 1.0000 1.0000 1.0000 18000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.2569 1.2430 1.12tO 1.2243 1.2175 1.1103 1.2033 1.2070 1.2165 1.223~---1 1.2331 1.2452 I
1.2642 1.2854 1.3055 1.3224 1.3354 1.3448 1.3504 1.3526 1.3514 1.3470 1.3397 1.3296 1.3169 1.3017 1.2848 1.2639 1.2435 1.2390 1.2363 1.2312 1.2243 1.2153 1.2043 1.1918 I
1.1789 1.1644 1.151\\
1.1373 1.1358 1.1470 1.1621 1.1762 1.11lO2 1.2042
.1.2182 1.2322 1.2462 1.2601 1.2735 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom S axial points excluded per Technical Specification B3.2.1.
Page 8 of 12
CORE OPERATING LIMITS REPORT, FNP UNIT l CYCLE 23 MARCH 2009 Figure 1 Rod Bank Insertion Limits verSus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 200 175 I 150
'l'
.J::. i
~ 125 II
~
C o
!E UI 100 o
Q,
"!:g
'B 75 0::
50 25 o
0.0 I
(.552,225)
(1,187) _
Banke (0,114)
BankO
(.070,0)
I I I I I 0.1 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 ~ 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.
Page 9of 12
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 23 MARCH 2009 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1
L.
~ 0.8 III
- u.
CJ) c:::
- i!
III CD D.
"0 0.6
.~
"i E o
z
~ 0.4 0.2 Core Height tft.)
KtZ) 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)
Page 10 of12
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 23 MARCH 2009 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC i
- a.
30 20 10 o
-60
-50
-40
-30
-20
-10 o
10 20 Axial Flux Difference (Delta I) %
30 40 50 60 120 110 100 90 Ci
~
80 0 a.
..J c(
- E 70 a::
w
- J:
~
60 0
I!:!
~
50 0
~
e....
~
40
(-12,100)
(+9,100)
I-UNACCEPTABLE I
~
UNACCEPTABLE 1/
\\
OPERATION I-OPERATION I
ACCEPTABLE ~
1/
OPERATION,
V
\\
(-30,50)
(+24,50)
Page 11 of12
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 23 MARCH 2009 Figure 4 Reactor Core Safety Limits 680 660 640
-<>- 2425 psig 2235 psig -1985 psig
-X-1825 psig 600 580 I UNACCEPTABLE I 10..
I OPERATION I
1'--"",
......... I'-- r--...
- 10.
...... I'--I'--
f"'., "
r--............
f"'., "
f"'.,
......... ~ "'-
I-I'--
roo r-....
........ r-....
r--...
1\\
Ix...
I'-.",
\\
I'--
I'--
\\
r-.....
r--....
r--
......1"-.
~
...... I'--
-r-....
\\
r......
r--....
I'-- r......
........ i"'--
~ r-....
I ACCEPTABLE 1
I"-.........
I OPERATION I
560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)
Page 12 ofl2