L-02-020, Cycle 16 Core Operating Limits Report
| ML022910027 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/15/2002 |
| From: | Beasley J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NEL-02-0206 | |
| Download: ML022910027 (19) | |
Text
Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205 992 7110 Fax 205 992 0403 October 15, 2002 Docket No.:
50-364 4w SOUTHERNhuul COMPANY Energy to Serve Your World NEL-02-0206 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 16 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 Farley Nuclear Plant Unit 2 Cycle 16.
If there are any questions, please advise.
Respectfully submitted, J.'i BasL ý,Jd'.
MGE/sdl: colr09.doc
Enclosure:
FNP Core Operating Limits Report Unit 2 - Cycle 16 J. Barnie Beasley, Jr., P.E.
Vice President
ý0 \\
Page 2 U. S. Nuclear Regulatory Commission cc:
Southern Nuclear Operating Company Mr. D. E. Grissette, General Manager - Farley U. S. Nuclear Regulatory Commission, Washington, D. C.
Mr. F. Rinaldi, Licensing Project Manager - Farley U. S. Nuclear Regulatory Commission, Region II Mr. L. A. Reyes, Regional Administrator Mr. T. P. Johnson, Senior Resident Inspector - Farley
ENCLOSURE Core Operating Limits Report Joseph M. Farley Nuclear Plant Unit 2 - Cycle 16 Revision 0 July 2002
JOSEPH M. FARLEY NUCLEAR PLANT CORE OPERATING LIMITS REPORT UNIT2 CYCLE 16 JULY 2002 REVISION 0 APPROVED FOR ISSUE:
/
DATE
-VTl
v vR.T....LIMITS.REPOR.
UIT2YC 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 16 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 (withk~ff> 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 klf < 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 AT (OTAT) and Overpower AT (OPAT) 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 Page 1 of 15 JULY 2002
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 ff 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.
2.2 SHUTDOWN MARGIN - MODES 2 (with k~f < 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (ker < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.
2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Ak/k.
2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOL/ARO/HZP-MTC shall be less than or equal to +0.7 x 104 Ak/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k/°F at 100 percent RTP.
The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 10-4 Ak/k/°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 104 Ak/k/°F.
The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 104 Ak/k/0F.
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 Page 2 of 15 JULY 2002 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16
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 - FQ (Z) (Specification 3.2.1)
- K(Z) for P > 0.5 P
F RTP FQ(Z)< 05- *K(Z) for P < 0.5 0.5 wher: P THERMAL POWER RATED THERMAL POWER 2.6.2 FRTP =2.50 2.6.3 K(Z) is provided in Figure 2.
Fg R TP
- g(z) 2.6.4 Fo(Z)<
To
- for P > 0.5 P,*W(Z) p RTP*K FQ(Z)5'Q
- K(Z) for P5 <0.5 0.5
- W(Z) 2.6.5 W(Z) values are provided in Figures 4 through 7.
2.6.6 The FQ(Z) penalty factors are provided in Table 1.
Page 3 of 15 JULY 2002 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16
2.7 Nuclear Enthalpy Rise Hot Channel Factor - FA. (Specification 3.2.2) 2.7.1 FN: <FrTP * (1 +PF
- (
P))
where:
P THERMAL POWER RATED THERMAL POWER 2.7.2 F4RTP = 1.70 2.7.3 PFAH = 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.'
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 8.
2.11 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT)
Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) 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 > 2209 psig;
- b. RCS average temperature < 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.
This concentration bounds the condition of keff* 0.95 (all rods in less the most reactive rod) and subcriticality (ail rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.
Page 4 of 15 JULY 2002 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Table 1 FQ(Z) PENALTY FACTOR Cycle FQ(Z)
Burnup Penalty (MWDJITU)
Factor 30 1.062 150 1.062 354 1.070 558 1.072 763 1.071 967 1.064 1171 1.054 1375 1.042 1579 1.030 1783 1.020 5663 1.021 5867 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 15 JULY 2002 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)
Setpoint Parameter Values T' < 577.20F K1= 1.17 "T, Ž 30 sec "T4 0 sec f1(AI) =
P'= 2235 psig K2 = 0.0 17/°F "12*< 4 sec "t5 < 6 sec
-2.48 {23 + (qt-qb)}
0% of RTP 2.05 {(qt-qb) - 15}
K3 = 0.000825/psi "T6 !< 6 sec when (qt - qb) < -23% RTP when -23% RTP < (qt -qb) -< 15% RTP when (qt - qb) > 15% RTP Page 6 of 15 JULY 2002 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)
Setpoint Parameter Values T" < 577.20F K4 = 1.10 K5 = 0.02/°F for increasing Tavg K5 = 0/°F for decreasing Tavg K6 = 0.00 109/°F when T > T" K6 = 0/ 0F when T < T" r3-10 sec "r4 0 sec
-r < 6 see "T6*5 6 see f2(AI) = 0% RTP for all Al Page 7 of 15 JULY 2002
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 F
200i I
175 Bank C_
S15 0
"(U C. 125 01
- (0, 114)
"i; 100 0
'0 75 0
50 25 0.0 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 8 of 15
JULY 2002 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 2
4 6
8 Core Height (feet) 10 12 Page 9 of 15 1.2 1_
0 0.8 LL 0~
O.2 N
N? 0.4 0.2 0
0
rn*r* (npTl AThIf, T.IMITR* RPPORT. FNP UNIT 2 CYCLE 16 JULY 2002 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC
(-12, 100)
(+9,10 UNACCEPTABLE t'
l::PFRATIAN
/ /
I I I
I I
UNACCEPTABLE OPERATION 120 110 100 90 S80 0
E 70 U
I "60 0
50 o 40 0
30 20
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (Delta I) %
Page 10 of 15 ACCEPTABLE OPERATION
(-30, 50)
(+24, 50) 10 U 5
-50 i
9 onwu n'DER A TWG I IMITS REPORT FNP UNIT 2 CYCLE 16
rrPi
flPT7R ATII'JC I.TMIT REPORT. FNP UMT 2 CYCLE 16
...A...JLLJ JA
JULY 2002 Figure 4 RAOC W(Z) at 150 MWVD/MTU 1.60 1.50 1.40 N 1.30 1.20 1.10 1.00 0
2 4
6 8
Core Height (feet) 10 12 This figure is referred to by Technical Specification B3.2. 1.
Axial Point Elevation (feet) 1200 BOL W(Z) 10000 2
1380 10000 3
11.60 10000 4
1140 10000 5
1120 10000 6
1100 10000 7
1080 10000 8
1060 10000 9
1040 10000 10 1020 10000 1
I 1000 12472 12 980 32382 13 960 1.2307 14 940 12242 15 920 12154 16 900 12041 17 880 12029 18 860 1.2082 19 840 1 2198 20 820 12280 21 800 12338 22 780 12375 23 760 12388 24 7.40 1.2383 25 720 12369 26 700 12335 27 680 12288 28 660 12225 29 640 12150 30 620 1.2065 31 600 1 1513 32 580 1 1401 33 560 1 1358 34 540 1 1466 35 520 1 1554 36 500 1.1633 37 480 1 1708 38 460 1 1772 39 440 1 1827 40 420 1 1872 41 400 1 1906 42 380 1.1930 43 360 1 1940 44 340 1 1944 45 320 1 1992 46 300 12099 47 280 12302 48 2.60 1.2573 49 240 12828 50 220 13082 51 200 13332 52 180 10000 53 160 10000 54 1
40 10000 55 1 20 10000 56 1 00 10000 57 080 10000 58 060 10000 59 040 30000 60 020 10000 61 000 10000 Top and Bottom 15% Excluded per Technical Specification B3 2 1.
Page 11 of 15 00-0 E OPER A TWG LIMITS REPORT FNP UNIT 2 CYCLE 16
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Figure 5 RAOC W(Z) at 4000 MWDJMTU 1.607 1.50 1.40 N 1.30 1.20 1.10 1.00 0
2 4
6 8
10 12 Core Height (feet)
This figure is referred to by Technical Specification B3.2.1.
Axial Point I
Elevation (feet) 1200 MOL-1 W(Z)
I 0000 2
11 80 10000 3
11 60 10000 4
1140 10000 5
1120 10000 6
1100 10000 7
1080 10000 8
1060 10000 9
1040 10000 10 1020 10000 11 1000 12747 12 980 1.2627 13 960 12497 14 940 12357 15 920 12210 16 900 12079 17 880 12097 18 860 12204 19 840 12283 20 820 1.2339 21 800 1 2370 22 780 12377 23 760 1 2361 24 740 1 2327 25 720 1 2280 26 700 12217 27 680 1.2138 28 660 12045 29 640 1 1939 30 620 1 1823 31 600 1 1472 32 580 1 1330 33 560 1 1223 34 540 1.1216 35 520 1 1265 36 500 1 1312 37 480 1 1348 38 460 1 1378 39 440 1 1404 40 420 11445 41 400 1 1476 42 3 80 1.1498 43 3.60 1 1510 44 340 11515 45 320 1 1517 46 300 1 1576 47 280 1 1751 48 260 1 1969 49 240 12184 50 2.20 1.2398 51 200 12610 52 1 80 10000 53 160 10000 54 140 10000 55 120 10000 56 100 10000 57 080 1.0000 58 060 10000 59 040 10000 60 020 10000 61 0 00 1 10000
- Top and Bottom 15% Excluded per Technia ntcification R3 2 I Page 12 of 15 L..
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Figure 6 RAOC W(Z) at 10000 MWDJMTU 1.60 1.50 +-
I I
I I
I I
I I
I I
I 1.40 11 11 1
1 111
-'-T--I I
1.30 1.20 1.10 -
1.00 0
2 Ax A
A A
4 6
E 10 12 Core Height (feet)
This figure is referred to by Technical Specification B3.2. 1.
Page 13 of 15 I
I I
Axial Elevation MOL-2 Point (feel)
W(Z) 1 1200 1.0000 2
11 80 10000 3
1160 10000 4
1140 10000 5
1120 10000 6
1100 10000 7
10 80 10000 8
1060 10000 9
1040 10000 10 10 20 10000 11 1000 12388 12 980 1.2360 13 960 12318 14 940 12272 15 920 12215 16 900 1.2133 17 880 1 2183 18 860 1 2320 19 840 1 2451 20 8.20 1.2554 21 800 12631 22 780 12680 23 760 12704 24 7.40 1 2702 25 720 12677 26 700 12640 27 680 1.2586 28 660 12510 29 640 1 2419 30 620 1 2309 31 600 1.1954 32 580 1 1804 33 560 1 1718 34 5 40 1 1718 35 5 20 1 171A 36 5 00
!I N69 37 4 80 1 1670 38 460 1 1631 39 4 40 1 1579 40 420 1 1515 41 400 1000 42opan Bo3o 15% Exlue pe3 43 3 60 1 1375 44 340 1 1311 45 3 20 1 1298 46 3 00 1.1363 47 2.80 1 1482 48 2 6o 1 1583 49 2 40 1 1688 50 2 20 I1792 51 2-00 T.1895 52 1 80 IT 0000 53 I160 IT0000 54 140 I00 55 12 0(
56 1 0 1 0000 57 0 80 I0000 5T8-0 60 1 0000 59 0 40 1 0000 60 0 20 1 0000 61 00 10000 r* Top and Botto'm 15% Excluded per ITechnical Speelfijcation B3 2 1
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Figure 7 RAOC W(Z) at 18000 MWD/MTU 1.60,
1.50 11 1
1 1
1 1.40 1.30 -
1.204-I I
I I
I I
I I
I I
1.00 0
2 A
7 A
4 6
8 10 12 Core Height (feet)
This figure is referred to by Technical Specification B 3.2.1.
Page 14 of 15
,A A
LhbAT 1.10 1 i
ý--!
1 1 -
I 1 1 - 1 1 7
Axial Elevation EOL Point (feet)
W(Z)
I 1200 10000 2
11.80 10000 3
1160 10000 4
1140 10000 5
1120 10000 6
1100 10000 7
1080 10000 8
1060 10000 9
1040 10000 10 1020 10000 11 1000 12175 12 980 12115 13 960 12089 14 9.40 1.2095 15 920 12136 16 900 12158 17 880 12147 18 860 12213 19 840 12442 20 820 12633 21 8 00 12793 22 780 12923 23 760 1.3021 24 740 1 3089 25 720 13126 26 700 13141 27 680 1 3136 28 660 1 3109 29 640 1 3059 30 620 12989 31 600 12648 32 580 1 2533 33 560 1 2465 34 540 12459 35 520 12431 36 500 12382 37 480 12316 38 460 12228 39 440 12119 40 420 1.1988 461 4000 10854 42 3 80 1 1732 43 3 60 1 1632 44 3a40 1
1550 45 3S20 1.1440 46 3 00 1 1456 47 2 80 1 1595 48 2 60 1 1766 49 2 40 1 1926 50 2 20 1-2083 51 2 00 1 2238 52 1 80 1 0000 53 160 10000 54 1 40 1 0000 55 1 20 1 0000 56 too0 1 0000 57 0 80 I 0000 58 0 60 I 0000 59 0 40 I 0000 60 1
0 20 1 0000 1
61 1
00 1
10000
- Top and Bottom 15%/ Excluded per Technical Specification B3 2 I
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 16 JULY 2002 Figure 8 Reactor Core Safety Limits 680 660 640 U
620 cc 1
600 580 560 Page 15 of 15
-- 0-2425 psig
-D-2235 psig 1985 psig
-X--1825 psig 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of Rated Thermal Power)