ML20035G092
| ML20035G092 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/14/1993 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20035G091 | List: |
| References | |
| NUDOCS 9304260145 | |
| Download: ML20035G092 (27) | |
Text
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l SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION I
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CORE OPERATING LIMITS REPORT CYCLE 8 i
Revision 0 April 14,1993 1
i V. C. Summer Nuclear Station l Core Operating Lirrits Report 9304260145 930421 Cycle 8, Revision 0 PDR ADOCK 05000395 P
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V. C. Summer Nuclear Station >
Core Operating Limits Report ;
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TABLE OF CONTENTS SECTION TITLE PAGE
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1.0 Core Operating Limits Report 1
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2.0 Operating Limits 2
l 2.1 Moderator Temperature Coefficient 2
2.2 Shutdown Rod Insertion Limits 2
2.3 Control Rod Insertion Limits 2
2.4 Axial Flux Difference 5
2.5 Heat Flux Hot Channel Factor-Fq(Z) 7 2.6 RCS Flow Rate and Nuclear Enthalpy 23 Rise Hot Channel Factor l
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l Core Operating Limits Report n
Cycle 8, Revision 0 i
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'V. C. SUMMER CYCLE 8 sceso 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for V. C. Summer Station Cycle 8 has been prepared in accordance with the requirements of Technical Specification 6.9.1.11.
The Technical Specifications affected by this :emrr are listed below:
i 3.1.1.3 Moderator Temperature Coefficient 3.1.3.5 Shutdown Rod Insertion Limit 3.1.3.6 Control Rod Insenion Limits 3.2.1 Axial Flux Difference 3.2.2 Heat Flux Hot Channel Factor 3.2.3 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor l
V. C. Summer Nuclear Station 1
Core Operating Limits Report j.
Cycle 8, Revision 0 I
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D ' V. C. Suuuta CYCLE 8 scua 2.0 OPERATING LBIITS 1
The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the 4
subsections which follow. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.11.
2.1 Moderator Temuerature Coefficient (Specification 3.1.1.3):
2.1.1 The Moderator Temperature Coefficient (MTC) limits are l
He BOL/ARO-MTC shall be less positive than the limits shown in Figure 1.
He EOUARO/RTP-MTC shall be less negative than -5x10' Ak/k/*F.
l 2.1.2 The MTC Surveillance limit is:
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The 300 ppm /ARO/RTP-MTC should be less negative than or equal to -4.1x10* Ak/k/*F.
where: BOL stands for Beginning-of-Cycle-Life ARO stands for All-Rods-Out RTP stands for RATED THERMAL POWER EOL stands for End-of-Cycle-Life 2.2 Shutdown Rod Insertion Limits (Specification 3.1.3.5):
The shutdown rods shall be withdrawn to at least 225 steps.
2.3 Control Rod Insertion Limits (Specification 3.1.3.6):
The Control Bank Insertion Limits are specified by Figure 2.
V. C. Summer Nuclear Station 2
Core Operating Limits Report Cycle 8, Revision 0
V. C. SUMMER CYCLE 8 scuo -
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Figure 1 i
Moderator Temperature Coemeient vs. Power Level V. C. Summer - Cycle 8 J
1
.9 UNACCEPTABLE OPERATION 4
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10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER V. C. Summer Nuclear Station 3
Core Operating Limits Report Cycle 8, Revision 0 i
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b V. C. SUMMER CYCLE 8 sceso Figure 2 i
Rod Group Inserte Ilmits vs. Thermal Power 1
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for Three Imop Operation t
V. C. Sununer - Cyde 8 RILLY a
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Core Operating Limits Report Cycle 8, Revision 0 4
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t b 'V. C. SUMhER CYCLE 8 SCEAG 2.4 Axial Flux Difference (Specification 3.2.1):
2.4.1 The Axial Flux Difference (AFD) Limits for RAOC operation for Cycle 8 are shown in Figure 3.
2.4.2 The Axial Flux Difference (AFD) target band during base load operations for Cycle 8 is:
BOL - EOL (0 - 19000 MWD /MTU): + or - 5% about a measured target value.
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2.4.2 The minimum allowable power level for base load operation, APL", is 85 % of RATED l.
THERMAL POWER.
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5 V. C. Summer Nuclear Station -
5 Core Operating Limits Report Cycle 8, Revision 0
b V. C. SUMMER CYCLE 8 -
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Figure 3 Axial Flux Difference Umits as a Function of Rated i
Therinal Power i
V. C. Sinn=wr - Cycle 8 l
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10 20 30 40 AXIAL FLUX DIFFERENCE (% AI) i V. C. Summer Nuclear Station 6
Core Operating Limits Report Cycle 8, Revision 0 i
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~b V. C. StS0JER CYCLE 8 j
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l 2.5 Heat Flux Hot Channel Factor - FJZ) (Specification 3.2.2)-
F" F (Z) s * =K(Z) for P > 0.5 n
F" F (Z)s * *K(Z) for Ps 0.5 n
0.5 E##
where: P = Rated Mrmal Power 2.5.1 F m = 2.45 q
2.5.2 K(Z) is provided in Figure 4 2.5.3 Elevation dependent W(z) values for RAOC operation at 150, 4000, 10000, and 16000 MWD /MTU are shown in Figures 5 through 8, respectively. This information is sufficient to determine W(z) versus core height in the range of 0 MWD /MTU to EOL burnup. Three point interpolation of the data in Figures 5 through 7 is sufficient to duermine RAOC W(z) versus core height between a Cycle burnup of 0 to 4000 MWD /MTU. For Cycle burnups between 4000 MWD /MTU and EOL burnup, W(z) versus core height may be obtained through three point interpolation of the data in Figures 6 through 8.
2.5.4 Elevation d: pendent W(z),ovalues for base load operation between 85 and 100% of rated thermal power with the item 2.4.2 specified target band about a measured target value at 150, 8000, and 16000 MWD /MTU are shown in Figures 9 through 11, respectively.
This informaaon is sufficient to determine W(z),e versus core height for burnups in the range of 0 MWD /MTU to EOL burnup through the use of three point interpolation.
V. C. Summer Nttelear Station 7
Core Operating Limits Report Cycle 8, Revision 0
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d V. C. SUMMER CYCLE 8 scesa 4
Fnpare 4 i
E(z) - Norw=Imal F (z) as a Function of Core Height o
.i V. C. Sinunwr - Cycle 8 i
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4 V. C. Summer Nuclear Station 8
Core Operating Limits Report Cycle 8, Revision 0 A
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j Figure 5 RAOC W(z) at 150 MWD /MTU l
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V. C. Summer Nuclear Station 9
Core Operating Limits Report Cycle 8, Revision 0
b '. C. SUhDdER CYCLE 8 V
scuo Data for Figure 5 RAOC W(z) at 150 MWD /MTU V. C. Summer - Cycle 8
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W Core Height Wg)
Core Heicht
.0000 1.0000 6.0800 1.1111
.1600 1.0000 6.2400 1.1192
.3200 1.0000 6.4000 1.1271
.4800 1.0000 6.5600 1.1342
.6400 1.0000 6.7200 1.1408
.8000 1.0000 6.8800 1.1466
.9600 1.0000 7.0400 1.1518 1.1200 1.0000 7.2000 1.1562.
1.2800 1.0000 7.3600 1.1599 1.4400 1.0000 7.5200 1.1628 1.6000 1.0000 7.6800 1.1649 1.7600 1.2816 7.8400 1.1661 1.9200 1.2600 8.0000 1.1665 I
2.0800 1.2379 8.1600 1.1662 2.2400 1.2157 8.3200 1.1650 2.4000 1.1936 8.4800 1.1628 2.5600 1.1717 8.6400 1.1601 2.7200 1.1510 8.8000 1.1590 2.8800 1.1300 8.9600 1.1634 3.0400 1.1084 9.1200 1.1750 3.2000 1.0982 9.2800 1.1922 3.3600 1.1006 9.4400 1.2120 3.5200 1.1018 9.6000 1.2324 3.6800 1.1014 9.7600 1.2532 i
3.8400 1.1016 9.9200 1.2741 4.0000 1.1016 10.0800 1.2950 4.1600 1.1012 10.2400 1.3157 4.3200 1.1006 10.4000 1.0000 4.4800 1.0997 10.5600 1.0000 4.6400 1.0984 10.7200 1.0000 4.8000 1.0968 10.8800 1.0000 4.9600 1.0948 11.0400 1.0000 l
5.1200 1.0924 11.2000 1.0000 l
5.2800 1.0897 11.3600 1.0000 5.4400 1.0862 11.5 JO 1.0000 5.6000 1.0845 11.6800 1.0000 5.7600 1.0915 11,8400 1.0000 l
5.9200 1.1023 12.0000 1.0000 t
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i V. C. Summer Nuclear Station 10 Core Opaating Limits Report Cycle 8, Revision 0 1
V. C. SUMMER CYCLE 8 sczaa Figure 6 RAOC W(z) at 4000 MWD /MTU V. C. Summer - Cycle 8 1.40 1.35 i
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V. C. Summer Nuclear Station 11 Core Operating Limits Report Cycle 8, Revision 0
i b 'V. C. SUMMER CYCLE 8 uno Data for Figure 6 RAOC W(z) at 4000 MWD /MTU V. C. Summer - Cyde 8 Core Heicht E
Core Height M
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.0000 1.0000 6.0800 1.1230
.1600 1.0000 6.2400 1.1334
.3200 1.0000 6.4000 1.1432
.4800 1.0000 6.5600 1.1523
.6400 1.0000 6.7200 1.1608
.8000 1.0000 6.8800 1.1686
.9600 1.0000 7.0400 1.1756 1.1200 1.0000 7.2000 1.1818 1.2800 1.0000 7.3600 1.1871 1.4400 1.0000 7.5200 1.1915 1.6000 1.0000 7.6800 1.1951 1.7600 1.2546 7.8400 1.1978 1.9200 1.2347 8.0000 1.1995 2.0800 1.2143 8.1600 1.2003 2.2400 1.1936 8.3200 1.2001 2.4000 1.1732 8.4800 1.1991 2.5600 1.1532 8.6400 1.1970 2.7200 1.1322 8.8000 1.1939 2.8800 1.1141 8.9600 1.1906 3.0400 1.1056 9.1200 1.1916 3.2000 1.1030 9.2800 1.2048 3.3600 1.1022 9.4400 1.2245 3.5200 1.1010 9.6000 1.2446 3.6800 1.0994 9.7600 1.2650 3.8400 1.0977 9.9200 1.2857 1
4.0000 1.0956 10.0800 1.3064 4.1600 1.0931 10.2400 1.3270 4.3200 1.0901 10.4000 1.0000 4.4800 1.0878 10.5600 1.0000 4.6400 1.0860 10.7200 1.0000 4.8000 1.0837 10.8800 1.0000 4.9600 1.0014 11.0400 1.0000 5.1200 1.0786 11.2000 1.0000 5.2800 1.0748 11.3600 1.0000 5.4400 1.0774 11.5200 1.0000 5.6000 1.0888 11.6800 1.0000 5.7600 1.1009 11.8400 1.0000 5.9200 1.1121 12.0000 1.0000 V. C. Summer Nuclear Station 12 Core Operating Limits Report l
Cycle 8, Revision 0 l
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b V. C. SUMMER CYCLE 8 scrao Figure 7 RAOC W(z) at 10000 MWD /MTU V. C. Summer - Cyde 8 l
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V. C. Summer Nuclear Station 13 Core Operating Limits Report Cycle 8, Revision 0
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b V. C. SUMMER CYCLE 8 scuo Data for Figure 7 RAOC W(z) at 10000 MWD /MTU V. C. Summer - Cycle 8 s
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. R1 W
Core Heicht Wg}
Core Height
.0000 1.0000 6.0800 1.1385
.1600 1.0000 6.2400 1.1453
.3200 1.0000 6.4000 1.1513 i
.4800 1.0000 6.5600 1.1562
.6400 1.0000 6.7200 1.1601
.8000 1.0000 6.8800 1.1629
.9600 1.0000 7.0400 1.1647 1.1200 1.0000 7.2000 1.1655 1.2800 1.0000 7.3600 1.1653 1.4400 1.0000 7.5200 1.1642 1.6000 1.0000 7.6800 1.1622 1.7600 1.1955 8.8400 1.1593 I
1.9200 1.1828 8.0000 1.1555 2.0800 1.1698 8.1600 1.1512 2.2400 1.1566 8.3200 1.1464 2.4000 1.1434 8.4800 1.1395 2.5600 1.1304 8.6400 1.1341 2.7200 1.1176 8.8000 1.1366 2.8800 1.1053 8.9600 1.1448 l
3.0400 1.0937 9.1200 1.1566 3.2000 1.0814 9.2800 1.1708 i
3.3600 1.0720 9.4400 1.1856 3.5200 1.0737 9.6000 1.2001 l
3.6800 1.0799 9.7600 1.2144 3.8400 1.0841 9.9200 1.2286 4.0000 1.0884 10.0800 1.2425 4.1600 1.0928 10.2400 1.2558 4.3200 1.0970 10.4000 1.0000 4.4800 1.1008 10.5600 1.0000 4.6400 1.1042 10.7200 1.0000 4.8000 1.1071 10.8800 1.0000 4.9600 1.1094 11.0400 1.0000 5.1200 1.1111 11.2000 1.0000 5.2800 1.1123 11.3600 1.0000 1
5.4400 1.1122 11.5200 1.0000 5.6000 1.1130 11.6800 1.0000 5.7600 1.1204 11.8400 1.0000 5.9200 1.1306 12.0000 1.0000 V. C. Summer Nuclear Station 14 Core Operating Limits Report Cycle 8, Revision 0
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i b 'V. C. SUMMER CYCLE 8 1
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,i scesa Figure 8 1
RAOC W(z) at 16000 MWD /AfIU h
V. C. Smnnwr - Cyde 8 1
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9 10 11 12 CORE HEIGHT (Feet)
V. C. Summer Nuclear Station 15 Core Operating Limits Report Cycle 8, Revision 0 7.
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b V. C. SUMMER CYCLE 8 l
scuo l
Data for Figure 8 RAOC W(z) at 16000 mVD/MTU V. C. Summer - Cycle 8 l
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W Core Heicht WE)
Core Height i
.0000 1.0000 6.0800 1.2367
.1600 1.0000 6.2400 1.2441 l
.3200 1.0000 6.4000 1.2501
.4800 1.0000 6.5600 1.2545
.6400 1.0000 6.7200 1.2574
.8000 1 0000 6.8800 1.2587
.9600 1.0000 7.0400 1.2586
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1.1200 1.0000 7.2000 1.2569 1.2800 1.0000 7.3600 1.2538 J
1.4400 1.0000 7.5200-1.2492 1.6000 1.0000 7.6800 1.2434 1.7600 1.2202 7.8400 1.2362 1.9200 1.2047 8.0000 1.2278 2.0800 1.1886 8.1600 1.2185 I
2.2400 1.1720 8.3200 1.2084 2.4000 1.1550 8.4800 1.1956 2.5600 1.1378 8.6400 1.1850 2.7200 1.1201 8.8000 1.1842 2.8800 1.1029 8.9600 1.1876 3.0400 1.0896 9.1200 1.1900 1
3.2000 1.0861 9.2800 1.1907 l
3.3600 1.0913 9.4400 1.1975 l
3.5200 1.0954 9.6000 1.2133 l
3.6800 1.0995 9.7600 1.2288 i
3.8400 1.1062 9.9200 1.2425 l
4.0000 1.1151 10.0800 1.2563 4.1600 1.1247 10.2400 1.26 %
4.3200 1.1333 10.4000 1.0000 i
4.4800 1.1411 10.5600 1.0000 4.6400 1.1484 10.7200 1.0000 4.8000 1.1550 10.8800 1.0000 4.9600 1.1589 11.0400 1.0000 5.1200 1.1637 11.2000 1.0000 5.2800 1.1773 11.3600 1.0000 5.4400 1.1932 11.5200 1.0000 5.6000 1.7060 11.6800 1.0000 5.7600 1.2174 11.8400 1.0000 5.9200 1.2279 12.0000 1.0000 V. C. Summer Nuclear Station 16 Core Operating Limits Report Cycle 8, Revision 0 l
b V. C. SUMMER CYCLE 8
=
i Figure 9 i
Basdood W(r) at 150 MWD /MTU l
V. C. Si-- Cyde 8 i
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9 10 11 12 CORE EIGHT (Feet) j i
1 V. C. Summer Nuclear Station 17 Core Operating Limits Report Cycle 8, Revision 0 4
1 b V. C. SUMMER CYCZ E 8 scuo l
Data for Figure 9 Baseload W(z) at 150 MWD /hfrU I
V. C. Summer - Cycle 8 l
Core Height E
Core Heicht E
.0000 1.0000 6.0800 1.0522
.1600 1.0000 6.2400 1.0500
.3200 1.0000 6.4000 1.0478 l
.4800 1.0000 6.5600 1.0454
.6400 1.0000 6.7200 1.0426
.8000 1.0000 6.8800 1.0399
.9600 1.0000 7.0400 1.0391 1.1200 1.0000 7.2000 1.0398 1.2800 1.0000 7.3600 1.0415 1.4400 1.0000 7.6800 1.0444 1.7600 1.0970 7.8400 1.0458 1.9200 1.0966 8.0000 1.0472 2.0800 1.0959 8.1600 1.0485 l
2.2400 1.0951 8.3200 1.0497 2.4000 1.0941 8.4800 1.0509 2.5600 1.0929 8.6400 1.0521 2.7200 1.0915 8.8000 1.0532 2.8800 1.0899 8.9600 1.0544 3.0400 1.0882 9.1200 1.0558 f
3.2000 1.0862 9.2800 1.0576 3.3600 1.0841 9.4400 1.0596 i
l 3.5200 1.0818 9.6000
- 1. % 13 3.6800 1.0797 9.7600 1.0630 l
3.8400 1.0779 9.9200 1.0647 l
4.0000 1.0763 10.0800 1.0662 4.1600 1.0748 10.2400 1.0675 l
l 4.3200 1.0732 10.4000 1.0000 4.4800 1.0715 10.5600 1.0000 4.6400 1.0696 10.7200 1.0000 4.8000 1.0676 10.8800 1.0000 4.9600 1.0655 11.0400 1.0000 5.1200 1.0632 11.2000 1.0000 5.2800 1.0609 11.3600 1.0000 5.4400 1.0589 11.5200 1.0000 5.6000 1.0575 11.6800 1.0000 5.7600 1.0559 11.8400 1.0000 5.9200 1.0541 12.0000 1.0000 V. C. Summer Nuclear Station l
18 Core Operating Limits Report i
[
Cycle 8, Revision 0 i
I
= -
V. C. St:MMER CYCLE 8 sense Figure 10 i
Bandoad W(z) at 8000 MWD /hfIU V. C. Sunumer - Cyde 8 I
1.15 1.14 l
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9 10 11 12 i
CORE HEIGHT (Feet)
V. C. SummerNuclear Station l
19 Core Operating Limits Report l.
Cycle 8, Revision 0 l
- - = = = = =
' V. C. SUMMER CYCLE 8 m:aan Data for Figure 10 I
Baseload W(r) at 8000 MWD /MTU j
V. C. Summer - Cycle 8
. G)
Core Heicht Wgl Core Heirbt W
4
.0000 1.0000 6.0800 1.0490
.1600 1.0000 6.2400 1.0465 r
j
.3200 1.0000 6.4000 1.0452 j
.4800 1.0000 6.5600 1.0457
.6400 1.0000 6.7200 1.0462
.8000 1.0000 6.8800 1.0467
.9600 1.0000 7.0400 1.0481 4
1.1200 1.0000 7.2000 1.0497 1
1.2800 1.0000 7.3600 1.0508 1.4400 1.0000 7.5200 1.0519 1.6000 1.0000 7.6800 1.0529 1.7600 1.1087 7.8400 1.0537 l
1.9200 1.1074 8.0000 1.0545 I
2.0800 1.1058 8.1600 1.0557 2.2400 1.1039 8.3200 1.0578 3
2.4000 1.1017 8.4800 1.0603 2.5600 1.0992 8.6400 1.0628
]
2.7200 1.0965 8.8000 1.0653 2.8800 1.0935 8.9600 1.0677 3.0400 1.0902 9.1200 1.0721 3.3600 1.0829 9.4400 1.0740 3.5200 1.0797 9.6000 1.0759 i
3.6800 1.0774 9.7600 1.0776 3.8400 1.0762 9.9200 1.0792 4.0000 1.0750 10.0800 1.0807 4.1600 1.0736 10.2400 1.0821 4.3200 1.0722 10.4000 1.0000 4.4800 1.0707 10.5600 1.0000 4.6400 1.0690 10.7200 1.0000 4.8000
'1.%72 10.8800 1.0000 4.9600 1.0653 11.0400 1.0000 5.1200 1.0632 11.2000 1.0000 5.2800 1.0611 11.3600 1.0000 5.4400 1.0589 11.5200 1.0000 5.6000 1.0565 i1.6500 1.0000 3.7600 1.0542 11.8400 1.0000 5.9200 1.0517 12.0000 1.0000 V. C. Summer Nuclear Station 3
Core Operating Limits Report Cycle 8, Revision 0
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.'b' V. C. SUMMER CYCLE 8 scaso Figure 11 Baseiosd W(r) at 16000 MWD /MTU V. C. Summer - Cycle 8 j
i 1.15 a
1.14 t
l L
1.13 I
1.12
,a i
a 1.11 a
A 1.10 A
1.09 i
A 4
l
- 1.08 i
O A
i
- 1.07
's.'t aa%"
&g 1.06
^
i aa, 1.05 1.04 1.03 1.02 1.01 1.00 0
1 2
3 4
5 6
7 8
9 10 11 12 CORE HEIGHT Eeet)
V. C. Summer Nuclear Station 21 Core Operating Limits Report Cycle 8, Revision 0
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i
' V. C. SUMMER CYCLE 8 scuo i
Data for Figure 11 I
Baseload W(r) at 16000 MWDSITU V. C. Sumnwr - Cycle 8 4
Core Heicht Wg)
Core Height
..(,2)
W
.0000 1.0000 6.0800 1.0598
.1600 1.0000 6.2400 1.0617
.3200 1.0000 6.4000 1.0632
.4800 1.0000 6.5600 1.0656
.8000 1.0000 6.8800 1.0664
.9600 1.0000 7.0400 1.0669 1.1200 1.0000 7.2000 1.0672 1.2800 1.0000 7.3600 1.0673 1.4400 1.0000 7.5200 1.0674 1.6000 1.0000 7.6800 1.0668 1.7600 1.1438 7.8400 1.0661 i
1.9200 1.1394 8.0000 1.% 81 2.0800 1.1344 8.1600 1.0720 j
2.2400 1.1289 8.3200 1.0759 2.4000 1.1228 8.4800 1.0796 2.5600 1.1164 8.6400 1,1832 2.7200 1.1094 8.8000 1.0867 2.8800 1.1022 8.9600 1.0899 3.0400 1.0949 9.1200 1.0933 3.2000 1.0869 9.2800 1.0974 3.3600 1.0794 9.4400 1.1017 i
3.5200 1.0766 9.6000 1.1054 3.6800 1.0760 9.7600 1.1088 3.8400 1.0751 9.9200 1.1119 4.0000 1.0741 10.0800 1.1145 4.1600 1.0730 10.2400 1.1166 4.3200 1.0718 10.4000 1.0000 4.4800 1.0704 10.5600 1.0000 4.6400 1.0688 10.7200 1.0000 4.8000 1.0671 10.8800 1.0000 4.9600 1.0653 11.0400 1.0000 5.1200 1.0633 11.2000 1.0000 5.2800 1.0613 11.3600 1.0000 5.4400 1.0588 11.5200 1.0000 5.6000 1.0563 11.6800 1.0000 5.7600 1.0561 11.8400 1.0000 5.9200 1.0577 12.0000 1.0000 V.C. Summer Nuclear Station 22 Core Operating Limits Report Cycle 8, Revision 0
'. C. SUMMER CYCLE 8 V
2.6 RCS Flow Rate and Nucicar Enthalov Rise Hot Channel Factor - F" (Specification 3.2-3):
R=
Fu *(1 + PFu * (I~F))
Where: P = Rated krmi Power 2.6.1 Fa"" = 1.56 2.6.2 PF,
= 0.3 2.6.3 The Acceptable Operation Region from the combination of Reactor Coolant System total flow and R is provi: led in Figure 12.
V. C. Summer Nuclear Station 23 Core Operating Limits Report Cycle 8, Revision 0
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'V. C. SUMMER CYCLE 8 scene Mgure 12 RCS Total Flow Rate vs. Three Imp Operation V. C. Sumuner - Cycle 8 MEASUREMENT UNCERTAINTIES OF 2.1% FOR FLOW AND 4.0% FOR INCORE MEASUREMENT OF FNAH ARE I
INCLUDED IN THIS FIGURE 32 i
ACCEPTABLE OPERATION REGION 30 e.
f I
W w
C C
(1.00,28.46) m g
28 g
.J
>C p
Av a:
UNACCEPTABLE 26 OPERATION REGION 1
l 24
.9
.95 1
1.05 1.1 R = FNAH/1.5Ii(1.0 + 0.I ' 4.
i i
V. C. Summer Nuclear Station l
74 Core Operating Limits Report Cycle 8 Revisionti l
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