ML020650403
| ML020650403 | |
| Person / Time | |
|---|---|
| Site: | Farley  (NPF-002, NPF-008) |
| Issue date: | 01/15/2002 |
| From: | Dennis Morey Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NEL-02-0008 | |
| Download: ML020650403 (36) | |
Text
Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 SOUTHERNA COMPANY Energy to Serve Your World" January 15, 2002 Docket Nos.:
NEL-02-0008 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Unit 1 Cycle 18 & Unit 2 Cycle 15 Core Operating Limits Report Revisions Ladies and Gentlemen:
In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) revisions for Farley Nuclear Plant.
The Unit 1 Cycle 18 Revision 1 and Unit 2 Cycle 15 Revision 1 COLRs were issued in conjunction with implementation of the "expanded" COLR approved by License Amendment Nos. 151 (NPF-2) and 143 (NPF-8).
If there are any questions, please advise.
Respectfully submitted, Dave Morey MGE/kw: colr07.doc
Enclosures:
FNP Core Operating Limits Report Unit I - Cycle 18 Revision 1 FNP Core Operating Limits Report Unit 2 - Cycle 15 Revision 1 iA) 4~2 f Dy Dave Morey Vice President Farley Project
Page 2 U. S. Nuclear Regulatory Commission cc:
Southern Nuclear Operating Company Mr. L. M. Stinson, 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 I Core Operating Limits Report Joseph M. Farley Nuclear Plant Unit 1 - Cycle 18 Revision 1 December 2001
JOSEPH M. FARLEY NUCLEAR PLANT CORE OPERATING LIMITS REPORT UNIT 1-CYCLE 18 DECEMBER 2001 REVISION 1 APPROVED FOR ISSUE:
OPERATIONS MANAGER DATE
4 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 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 SHUrDOWN MARGIN - MODES I and 2 (with kfi> 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 kc < 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 - Fg (Z) 3.2.2 Nuclear Enthalpy Rise Hot Channmel Factor - Fwt*
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
A CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 18 DECEMBER 2001 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 I AND 2 (with k,_
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 kr_ < 1.0). 3. 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (k'r < 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 10"4 Ak/k/PF for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k/OF at 100 percent RTP.
The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 104 Ak/k/0 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/0F.
The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 104 Ak/k/WF.
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
4 CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 18 DECEMBER 2001 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) 2.6.1 F,(Z)_<-Q *K(Z) for P > 0.5 P
F (Z)<!gQ *K(Z) for P5 <0.5
0.5 where
P THERMALPOWER RATEDTHERMALPOWER 2.6.2 FCz7 =2.50 2.6.3 K(Z) is provided in Figure 2.
2.6.4 Fg(Z)<_F, K(Z) forP>0.5 P *W(Z)
FC?(Z)J<- Fgn
- K(Z) forP50.5 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
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FN (Specification 3.2.2) 2.7.1 F;
FRTP *(I+PF,, * (l-P))
where: PTHERMAL POWER where:
P =
RA TED THERMAL POWER 2.7.2 Ffr =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.
2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES I 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 (OPAlI 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 < 580.30F; 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 kff< 0.95 (all rods in less the most reactive rod) and subcriticality (aJi rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B'0 depletion.
Page 4 of 15
AM "
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCL+E 18 DECEMBER 2001 Table 1 FQ(Z) PENALTY FACTOR Cycle
- Burnup, (MWD/MTU) 4644 4848 5052 5256 FQ(Z)
Penalty Factor 1.020 1.023 1.021 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 burnup at which the FQ(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.
Page 5 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)
Setpoint Parameter Values T' < 577.20F Ki = 1.17
,ri > 30 sec T4 = 0sec F = 2235 psig K2 = 0.017/-F T2 <4 sec r *6 sec K3 = 0.000825/psi
- 6 *6 sec
-2.48 123 + (qt - qb)}
0% of RTP 2.05 I(qt - qb) - 151 when (qt - qb) < -23% RTP when -23% RTP < (qt - qb) < 15% RTP when (qt - qb) > 15% RTP Page 6 of 15 f1(Ai) =
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)
Setpoint Parameter Values T" < 577.20F K 4
= 1.10 YK5 = 0.02/°F for increasing Tavg Ks = 0/OF for decreasing Tavg K6 = 0.00109/OF when T > T" K6 = 0/0 F when T < T" T3 -a 10 sec T4 =-0sec
.5 <6 sec
¶t6*:6 sec f2(AI) = 0% RTP for all Al Page 7 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 175 I
.5,25 1250
. 00 50 25 I-(.Io o)A I I
- II A
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 Ž_225 and I
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
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 I-o.
0 v~ 0.8 0
0 0
2 4
6 8
10 Core Height (feet) 12 Page 9 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC II1[FI I I I I
I F2-v-fl z
II I
(-12, 100)
(+9, 100)
UNACCEPTABLE n
h
.,ib~i t
I I
I I
UNACCEPTABLE OPERATION so J
L ACCEPTABLE 70 OPERATION
(-30,50)
(+24,50) 30 20
- 10. 0.O 1 1 a-------------------
-40
-30
-20
-10 0
10 20 30 Axial Flux Difference (Delta I) %
40 s0 Page 10 of 15 1
120 110 100 90 I-.
-50 I
4%k CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 Figure 4 RAOC W(Z) at 150 MWDIMTU DECEMBER 2001 1.60 1.50 1.40 A
A S1.30 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.
AX Elvto BOL I'oimt (feet)
W(Z) 1 12.00 1.0001 2
1 1.80 1.00(00 3
81.60 1.0871 4
81.40 1.1982 5
81.20 1.206 6
8I.00 1.2OO1 2
10.80 1.2OO 2
10.60 1.2010 9
10.40
.2OOOO 25 10.20 I.oo20 26 10.00 1.2141 12 9.80 1.2076 13 9.60 1.2024 14 9.40 1.1975 15 96.20 1.1911 16 9.00 1.1812 17 5.80 1.1783 33 8.60 1.1871 19 8.40 1.132 20 8.20 1.2069 21 8.00 1.2134 22 7.80 1.2178 23 7.60 1.2201 24 7.40 1.2000 25 7.20 1.201 26 7.00 1.2106 27 6.80 1.2156 1
28 6.60 1.0011 29 6.40 1.200 30 6.20 1.1900 31 6.00 1.1908 32 5.80 1.1840 33
- 5. 60 1.1948 34 5.40 1.1951 35 5.20 1.2068 36 5.OO 1.2180 37 4.90 1.2287 1 38 4.60 1.2M8 39 4.40 1.2470 40 4.20 1.2546 41 4.00 1.29 42 3.80 1.2661 43 3.60 1.2698 44 3.40 1.2734 45 3-20 1.2819 46 3.00 112M0 47 2.80 1.3072 4.8 2.60 ISM35 49 2.40 1.3624 50 2.20 1.3892 51 2-0O 1A4156
- 52 1.90 l.OOOO 53 1.60 1.0O00 54 1.40 1.0000 55 1.2D 1.0O00 56 1.00 1.OO0 57 0.80 1.0000 58 0.60 11.0O00
- 59 0NO 1.0(000
- 60 0.20 1.000 61 0.00 i.0000
- Top md Bottom 15% Excluded per Tedvchnc Specification B3.2.1.
Page 11 of 15 L-
EX CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 Figure 5 RAOC W(Z) at 4000 MWDIMTU DECEMBER 2001 1.60 1.50 1.40 1.30 A LA AA 1.20 A
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 Elevaion MOL-1 Point f
(
I 12.00 1.0000 2
11.80 1.0000 3
11.60 1.0000 4
11.40 1.0000 5
11.20 1.0000 6
1.00 1.0000 7
10.80 1.0000 8
10.60 1.0000 9
10.40 1.0000 10 10.20 1.0000 I
1 10.00 1.2512 12 9.80 1.2412 13 9.60 1.2303 14 9.40 1.2185 Is 9.20 1.205 16 9.00 1.1931 17 3.80 1.1928 18 8.60 1.2049 19 8.40 1.2139 20 8.20 1.2205 21 8.00 1.2248 22 7.80 1.2268 23 7.60 1.2266 24 7.40 1.2243 25 7.20 1.2208 26 7.00 1.2158 27 6.80 1.2093 28 6.60 1.2013 29 6.40 1.1921 30 6.20 1.1817 31 6.00 1.1708 32 5.80 1.1574 33 5.60 1.1479 34 5.40 1.1502 35 5.20 1.1569 36 5.00 1.1632 37 4.80 1.1687 38 4.60 1.1687 39 4.40 1.1775 40 4.20 1.1804 41 4.00 1.1826 42 3.80 1.1835 43 3.60 1.1842 44 3.40 11861 45 3.20 1.1866 46 3.00 1.1955 47 2.80 1.2119 48 2.60 1.2334 49 2.40 1.2557 50 2.20 1.2779 51 2.00 1.2997 52 1.80 1.0000 53 1.60 1.0000 54 1.40 1.00D0 55 1.20 1.0000 56 1.00 1.0000 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20 L.0000 61 0.00 1.0000 STop ec Bottom 15% E2xcluded per Technical Specification B3.711.
Page 12 of 15
k~
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 6 RAOC W(Z) at 10000 MWDIMTU 1.60, 1.50 1.40 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.
point fe)
W(Z) 1 1200 1.0000 2
11.80 1.0000 3
11.60 1.0000 0
4 11.40 1.0000 5
11.20 1.0000 6
11.00 1.0000 7
10.30 1.0000 8
1 10.60 1.0000 9
1 10.40 1.0300 ol 10 1
10.20 1.50000 2I 10.00 1.2482 12 9.30 1.2377 13 9.60 1.2323 14 9.40 1.2262 25 9.20 1.2196 16 9.00 1.2116 17 8.80 1.2M75 28 6.60 1.2590 19 8.40 1.2444 20 8.20 1.2%91 21 8.00 1.2650 22 7.80 1.213 23 7.60 1.2747 24 7.40 1.2755 25 7.20 1.1965 26 7.00 1.2194 27 6,80 1.1659 28 6.60 1.2590 29 6.40 1.200 30 6.20 1.2397 31 6000 12.200 32 a.80 1.2136 S33 5.60 1.2007 34 5.40 1.1972 35 5.20 1.1965 36 5.00 1.1949 37 4.80 1.1919 38 4.60 1A875 39 4.40 1.1821 40 4.20 1.1753 41 4.00 1.1695 42 3.80 1.1629 43 3.60-1.1595 44 3.40 1.1559 45 3.20 1.1517 46 3.00 1.49 47 2-80 1A559 48 2.60 1.1607 49 2.40 1.1680 5o 2.20 IA777 51 2.00 1AS76 52 1
1.80 1.0000 53 1
1.60 i.0000 54 1
1.40 1.0000 55 1.20
!.00OD
- 1 56 1.00 1.0000 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20
!.0000 61 0-00 1.00 T
aTop Sd Bauoma 15% Etu dBed p TedaficaW Specficaumai B3.1 1.
Page 13 of 15
4.A CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 Figure 7 RAOC W(Z) at 18000 MWDIMTU DECEMBER 2001 1.60 I
I I-1.50 1.20 A
A
~1.30 A
A 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 Elevation EOL point (feet)
Wz 1
17.00 1.0000 2
11.80 1.0000 3
11.60 1.0000 4
11.40 1.0000 5
11.20 1.0000 6
11.00 1.0000 7
10.80 1.0000 8
10.60 1.0000 9
10.40 1.0000 10 10.20 1.0000 11 10.00 1.2352 12 9.80 1.2287 13 9.60 1.2245 14 9.40 1.2216 15 9.20 1.2294 16 9.00 1.2499 17 8.80 1.2717 "18 8.60 1.2897 19 1.40 1.3097 20 2.20 1.3289 21 2.00 1.3447 22 7.80 1.3564 23 7.60 1.3645 24 7.40 1.3688 25 7.20 13696 26 7.00 1.3670 27 6.20 1.3614 28 6.60 1.3528 29 6.40 1.3417 30 6.20 13280 31 6.00 1.3125 32 5.*0 1.2939 33 5.60 1.2754 34 5.40 1.2686 35 5.20 1.2662 36 5.00 1.2621 37 4.80 1.2559 38 4.60 1.2480 39 4.40 1.2387 40 4.20 1.2274 41 4.0O 1.2143 42 3.80 1.1991 43 3.60 11850 44 3.40 1.1754 45 3.20 1.1632 46 3.00 1.1628 47 2.80 1.1760 48 2.60 1.1930 49 2.40 1.2091 50 2.20 1.2248 51 2.00 1.2405f 52 1.80 1.0000 53 1.60 1.0000 54 1.40 1.0000 55 1.20 1.0000 56 1.00 1.0000 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 S
60 0.20 1.0000 61 0.00 1.0000 Page 14 of 15 T--'=:cal S-4ficmt:on B3 2 1
- Top wad Boatto 15% Excluded per
k CORE. OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 8 Reactor Core Safety Limits 680 660 640
- 62.
6 1-0.8 1.0 UNACCEPTABLE OPERATION I L I
II ACCEPTABLE OPERATION-4 01+/-
1.2 Power (Fraction of Rated Thermal Power)
Page 15 of 15 2425 psig
-- a-2235 psig 1985 ps1g
-X-1825 psig 0.0 0.2 0.4 0.6 58(
56(
ENCLOSURE II Core Operating Limits Report Joseph M. Farley Nuclear Plant Unit 2 - Cycle 15 Revision 1 December 2001
JOSEPH M. FARLEY NUCLEAR PLANT CORE OPERATING LIMITS REPORT UNIT 2 - CYCLE 15 DECEMBER 2001 REVISION 1 APPROVED FOR ISSUE:
OPERATIONS MANAGER
/3. 0t DArTEp
.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 15 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 kff> 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 kff< 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
A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER2001 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 I AND 2 (with k&I > 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& < 1.0). 3. 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kfr < 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 10-4 Ak/k/*F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k/0F at 100 percent RTP.
The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 104 Ak/k/0F.
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 Ak/k/oF.
The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 10-4 Ak/k/0F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out I-IZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER Page 2 of 15
A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 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 - FC (Z) (Specification 3.2. 1)
2.6.1 FQ(Z)
<-Q
- K(Z)
P FRlP 5 *K(Z) for P > 0.5 for P: <0.5 where:
P =
THERMALPOWER RATED THERMALPOWER 2.6.2 FjRrp =2.50 2.6.3 K(Z) is provided in Figure 2.
2.6.4 F2 (Z) 5 FP
- K(Z)
-P*W(Z)
Fe(Z)< F W(Z)
FQ()*0.5*W(Z) for P > 0.5 for P < 0.5 W(Z) values are provided in Figures 4 through 7.
The F. (Z) penalty factors are provided in Table 1.
Page 3 of 15 2.6.5 2.6.6
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FN, (Specification 3.2.2) 2.7.1 F*
Frp (I+PF * (-P))
where:
P THERMALPOWER RATED THERMAL POWER 2.7.2 F"
= 1.70 2.7.3 PFI = 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 (OPAlT) 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 Ž 264,200 GPM when using the elbow tap method.
This concentration bounds the condition of kafr<* 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.
Page 4 of 15
.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Table 1 FQ(Z) PENALTY FACTOR Cycle FQ(Z)
Burnup Penalty (MWD/MTU)
Factor 30 1.029 354 1.031 557 1.031 761 1.029 965 1.026 1372 1.020 4428 1.020 4632 1.021 4836 1.029 5040 1.038 5243 1.036 6262 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 burnup 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
.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Table 2 DECEMBER 2001 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)
Setpoint Parameter Limits T' _ 577.20F Ki = 1.17 Ti;> 30 sec 4 = 0 sec P' =2235 psig K2 = 0.017/'F T2 <4 sec
'rs5 6 sec K3 = 0.000825/psi T:5 6 sec
-2.48 423 + (qt - qb}
0% of RTP 2.05 {(qt - qb) - 151 when (qt-qb) -- -23% RTP when -23% RTP < (qt -qb) *15% RTP when (qt - qb) > 15% RTP Page 6 of 15 I
fi(AI) =
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)
Setpoint Parameter Values T" < 577.20F K4 = 1.10 I, = 0.02/ 0 F for increasing T.vg Ks = 0/*F for decreasing T.vg K6 = 0.00109/°F when T > T" K6 = 0/OF when T5
<T" T3 10 sec 4 =0 sec cs *6 sec
'6 <6 sec f2(AI) = 0% RTP for all AI Page 7 of 15 DECEMBER 2001
4.COEOEAIGLTREOT NUNT2CCE1 COEOPRFIGLIIS EOTFP NT YCE1 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive DECEMBER 2001 225 200 175 S150
- c. 125 0
00 50 25
.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
(.552, 225)
I(1I1I7IA
_Bank C_
I
.~,o
,,,,,I 0
0.0 0.
1
DECEMBER 2001
.CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 0
2 4
6 8
10 Core Height (feet) 12 Page 9 of 15 1.2 0 SO.8 LL CD v 0.6 0
Z ti 0.4 0.2 0
k CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC U I I I UNACCEPTABLE
(-12,100) 9 I
UNACCEPTABLE OPERATION
-ACCEPTABLE_
OPERATION
(-30, 50)
(+24, 50)
-50
-40
-30
-20
-10 0
10 20 Axial Flux Difference (Delta I) %
30 40 I -
I 50 Page 10 of 15 120 110 100 90
- o 80
- s.
S70 S
1-.
S60
'V s
S50 40 0
IL 30 20 10 0
\\
4A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Figure 4 RAOC W(Z) at 150 MWD/MTU 1.60 1.50 1.40 N S1.3o 1.20 1.10 1.00 0
2 4
6 8
10 12 Core Height (feet)
Axial Elevation BOL Point 0feeA)
W(Z) 1 12.00 1.0000 2
11.80 1.0000 3
11.60 1.0000 4
11.40 1.0000 5
I 1.20 1.0000 6
11.00 1.o0000 7
10.30 1.0000 8
10.60 1.o0o0 9
10.40 1.0000 60 10.20 1.0000 I 1 10.00 1.1830 12 9.80 1.179B 1
13 9.60 1.1790 14 9.40 1.1736 15 9.20 1-1682 16 9.00 1.1600 17 8.80 1.1582 18 8.60 1.1686 19 1
8.40 1.1913 20 1
8.20 1.1919 21 1
8.00 1.2003 22 1
7.90 1.2067 23 1
7.60 1.2112 24 7.40 1.2138 25 7.20 125 26 7.00 1.2158 27 6.80 1.2143 28 6.6o 1.2116 29 6.4 1.2075 30 6.20 1.2026 31 6.00 1.1957 32 5.80 1.1929 33 5.60 1.1955 34 5.40 i1.2082 35 1
5.20 1.2205 36 5.00 1.2318 37 4.90 1.2423 38 4.60 1.2516 39 4.40 1.2600 40 4.20 1.26 41 4,00 1.2726 42 3.10 1.m2770 43 3.60 i1.2830 44 3.40 1.2920 45 3.20 1.3049 46 3.00 1.3197 47 1
2ISO 1.*3362 48 1
2.60 1.3%68 49 2.40 1.3813 50 2.20 1.4056 51 2.00 1.4290 52 1.90 11.0000 53 1.60 i.0000 54 1.40 1.0000 55 1.20 1.0000 56 1.00 1.0000 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.G000 60 0203 1.0q0 61 0.00 1.000
- Top and Bottom 15% Excludedpe Technical Spe-ification B3.2.1.
This figure is referred to by Technical Specification B3.2.1.
Page 11 of 15
A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Figure 5 RAOC W(Z) at 4000 MWD/MTU 1.60 1.50 1.40 1.30 A
A 1.20 1.10-1.00.
0 2
4 6
8 10 12 Core Height (feet)
Axial EIcvaion MOL.-1 Point (fed)
WM 1
12.00 1.0000 2
11.80 1.0000 3
A1.60 1.0000 4
11.40 1.0000 5
11.20 1.{000 6
11.00 1.0000 7
10.80 1.0000 8
10.60 1.0000 9
10.40 1.0000 10 10.20 1.0000 11 10.00 1.2231 12 9.80 1.2155 13 9.60 1.2093 14 9.40 1.2020 15 9.20 1.1964 16 9.00 1.1890 17 8.80 1.1881 18 8.60 1.1987 19 8.40 1.2087 20 8.20 1.2162 21 8.00 1.2215 22 7.80 1.2243 23 7.60 1.2249 24 7.40 1.2234 25 7.20 1.2208 26 7.00 1.2166 27 6.80 1.2106 28 6.60 1.2033 29 6.40 1.1946 30 6.20 1L1346 31 6.00 1.1744 32 5.80 1.1608 33 5.60 1.1530 34 5.40 1.1611 35 5.20 1.1690 36 5.00 1.1752 37 4.80 1.1813 38 4.60 1.1863 39 4.40 1.1903 40 4.20 1.1934 41 4.00 1.1958 42 3.80 1.1973 43 3.60 1.1982 44 3.40 1.2012 45 3.20 1.2066 46 3.00 1.2185 47 2.80 1.2377 48 2.60 1.2606 49 2.40 1.2828 50 2.20 1048 51 2.00 1.3263 52 1.80 1.000D 53 1.60 1.0000 a
54 1.40
!.0000 55 1.20 1.0000 a
56 1.00 1.0000 a
57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20 1.0000 61 0.00 i.0000 T
Top anl Bottom 15% ExB.uded per Technical Specification B33.2. 1.
This figure is referred to by Technical Specification B3.2.1.
Page 12 of 15
k CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Figure 6 RAOC W(Z) at 10000 MWDIMTU 1.60 1.50 1.40 1.30 1.2(
1.1(
1.0 AA AA 0--------------
0 t0 0
2 4
6 8
10 12 Core Height (feet)
S Axial point 2
(feet) 12.00 11.30 11i(.#
MOL-2 LOODO 1.0000 1 0"0 4
1 1.40 1.0000 5
11.20 1.0000 6
11.00 1.0000 7
10.80 1.0000 8
10.60 1.0000 9
10.40 1.0000 10 10.20 1.0000 11 10.00 1.2585 12 9.30 1.2537 13 9.60 1.2482 14 9.40 1.2415 15 9.20 1.2342 16 9.00 1.2238 17 8.80 1.2283 18 8.60 1.2420 19 8.40 1.2567 20 8.20 1.2687 21 8.00 1.2776 22 7.80 1.2837 23 7.60 1.2069 24 7.40 1.2874 25 7.20 1.2954 26 7.00 1.2819 27 6.80 1.2764 28 6.60 1.2687 29 6.40 1.2591 30 6.20 1.2475 31 6.00 1.2349 32 5.80 1.2199 33 5.60 1.2052 34 5.40 1.1974 35 5.20 1.1955 36 15.00 1.1942 37 4.80 1.1913 38 4.60 1.1073 39 4.40 1.1820 40 4.20 1.1756 41 4.00 1.1681 42 3TB 0 1.1615 43 3.60
.1.1 545 44 3.40 1.1473 45 3.20
- 1. 1422 46 3.00 1.1404 47 2.80 i.1467 48 2.60 1.1562 49 2.40 1.1662 50 2.20 1.1761 51 2.0 1.1859 52 1.8 1.0(000 3
1.60 1.0000 54 1.40 1.0(000 55 1.20 1.0000 56 1.00 i.0O00 57 0.80
!.(0 58 0.60 1.0000 59 0.40 1.0O00 60 0.20 i1.0O00 61 0.(30 1.0000 STop end Botom 15%
F xcluded per Tedinical Specification B3.2. 1.
This figure is referred to by Technical Specification B3.2.1.
Page 13 of 15
.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Figure 7 RAOC W(Z) at 17000 MWD/MTU DECEMBER 2001 1.60 1.50 1.40 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 Elevation EOL Point (feet)
WCZ 1
12.00 1.0000 S 2 11.80 1.0000 3
1.60 1.0000 4
11.40 1.0000 5
11.20 1.0000 6
11.00 1.0000 7
10.80 1.0000 9
10.40 1.0000 10 10.20 1.0000 21 10.00 1.2470 12 9.80 1.2392 13 9.60 1.2301 14 9.40 1.2256 "15 9.20 1.2210 16 9.00 1.2152 17 4.80 1.2107 38 4.60 1.2139 19 8.40 1.2383 20 8.20 1.2593 21 4.00 1.2764 22 7.80 1.2910 23 7.60 1.3022 24 7.40 1.3103 25 7.20 1.3153 26 7.00 1.3178 27 6.80 1.3184 28 6.60 1.3166 29 6.40 1.3124 1
30 6.20 1.3059 31 6.00 1.2976 32 1
5.90 1.2961 33 5.60 1.2753 34 5a40 1.2%
x 35 5.20 1.2698 1
36 5.00 1.2650 37 4.80 1.2582 39 4.60
!.2m493 39 4.40 1.2382 1
40 4.20 1.2250 41 4.00 1.2100 42 3.10 1.1989
,43 1
3.60 1.1875 44 1.40 1.7"45 45 3.20 1.1598 46 3.00 1.1596 47 2.80 1.1724 48 2-60 1.1870 1
49 2.40 1.2009 50 2.20 1.2149_
51 2.00 1.2289 0
53 1.60 1.0000 54 1.40 1.0000
- 52 1.90 1.0000 55 C.20 1.0*00 56 1.00 1.0000 57
- 0. so 1.0000 58 0.60 L.OON0 S
59 0.40 1.0000 60 0.20 1.0000 61 5.56 i.om0
- Top wd Bottomi IS% ExclUded per Technical Specification 133.2. 1.
Page 14 of 15
DECEMBER 2001
.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Figure 8 Reactor Core Safety Limits 680 660 640 U
co 620 600 580 560 1.2 Page 15 of 15
..-¢-2425 psig
--a--2235 psigj 6-
-1985 psig
--X-- 1825 psig 0.0 0.2 0.4 0.6 0.8 1.0 Power (Fraction of Rated Thermal Power)