NL-18-0661, Cycle 29 Core Operating Limits Report
| ML18136A990 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/16/2018 |
| From: | Gayheart C Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-18-0661 | |
| Download: ML18136A990 (18) | |
Text
.t. Southern Nuclear MAY 1 6 2018 Docket Nos.: 50-348 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Regulatory Affairs Joseph M. Farley Nuclear Plant-Unit 1 Cycle 29 Core Operating Limits Report Ladies and Gentlemen:
40 Inverness Center Parkway Post Off1ce Box 1295 Birmingham, AL 35242 205 992 5000 tel 205 992 7601 fax NL-18-0661 In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLR) for the Joseph M. Farley Nuclear Plant (FNP) - Unit 1 Cycle 29 Version 1.
This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.
Respectfully submitted,
Enclosure:
Core Operating Limits Report for FNP Unit 1 Cycle 29 Version 1 cc:
Regional Administrator, Region II NRR Project Manager-Farley Nuclear Plant Senior Resident Inspector-Farley Nuclear Plant RTYPE: CFA04.054
Joseph M. Farley Nuclear Plant-Unit 1 Cycle 29 Core Operating Limits Report Enclosure Core Operating limits Report for FNP Unit 1 Cycle 29 Version 1
SOUTHERN A COMPANY Energy to Serve Your World" Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 29 Version 1 December 2017
- This record was final approved on 12/20/2017 1:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 2017 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT I CYCLE 29 has been prepared in accordance with the requirements ofTechnical Specification 5.6.5.
The Technical Requirement affected by this report is listed below:
13.1.1 SHUTDOWN MARGIN-MODES I and 2 (with k.tr::=:: 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 k.tr< 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-FtJ.~
3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower ~T (OP~T) 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
- This record was final approved on 12120/2017 1 :10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERA TlNG LlMlTS REPORT, FNP UNIT 1 CYCLE 29 December 2017 2.0 OPERATING LlMITS 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.rr ~ 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent dk!k.
2.2 SHUTDOWN MARGIN-MODES 2 (with kill< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (k.rr < 1.0), 3 and 4-The SHUTDOWN MARGIN shall be greater than or equal to 1. 77 percent dk/k.
2.2.2 Mode 5-The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent dk/k.
Page 2 of 15
- This record was final approved on 12/20/20171 :10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 20 I7 2.3 Moderator Temperature Coefficient (Specification 3.I.3) 2.3.I The Moderator Temperature Coefficient (MTC) limits are:
The BOLIARO-MTC shall be less than or equal to +0.7 x 10-4 llklk/°F for power levels up to 70 percent RTP with a linear ramp to 0 llklki°F at I 00 percent RTP.
The EOLIARO/RTP-MTC shall be less negative than -4.3 x 10-4.:\\k/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 I 0-4.:\\klk/°F.
The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5 and the following algorithm:
Revised Predicted MTC== Predicted MTC* + AFD Correction** + Predictive Correction***
- where,
- Predicted MTC is calculated from Figure 5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
- AFD Correction is the more negative value of:
{0 pcmrF or (MFD
- AFD Sensitivity)}
where: MFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm, AFD Sensitivity== 0.07 pcmrF I MFD
- Predictive Correction is -3 pcmrF.
The IOO ppm/ARO/RTP-MTC should be less negative than -4.0 x I0-4.:\\k/k/°F.
where: BOL stands for Beginning of Cycle 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.I.5) 2.4.I The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.
Page 3 of 15
- This record was final approved on 12120/2017 1 :10:32 PM. ( This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 29 December 2017 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 l.
2.6 Heat Flux Hot Channel Factor-FQ (Z) (Specification 3.2.1) for P > 0.5 for P ~ 0.5 where:
THERMAL POWER p = ----------
RATEDTHERMALPOWER 2.6.2 F~ TI' = 2.50 2.6.3 K(Z) is provided in Figure 2.
2.6.4 FRTI' *K(Z)
F (Z) < -=-
0- ---
Q P*W(Z)
FRTP *K(Z)
F (Z) < --=-Q ---
Q 0.5*W(Z) for P > 0.5 for P ~ 0.5 2.6.5 Full Power W(Z) values are provided in Table 4.
Part Power (48% RTP) W(Z) values are provided in Table 5.
2.6.6 The FQ(Z) penalty factors are provided in Table 1.
Page 4 of 15
- This record was final approved on 12/20/20171:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 2017 2.7 Nuclear Enthalpy Rise Hot Channel Factor-F~ (Specification 3.2.2) 2.7.1 F~ 5:F://*(l+PFilH *(1-P))
where:
THERMAL POWER p = ----------
RATED THERMAL POWER 2.7.2 F!::~' = 1.70 2.7.3 PFilH =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) 2.1 0.1 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 4.
2.11 Reactor Trip System Instrumentation Overtemperature !l T COT !l T) and Overpower !l T COP!l T)
Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature !l T (OT !l T) and Overpower
!lT (OP!lT) setpoint parameter values forTS 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 ~ 580.3°F; and
- c.
The minimum RCS total flow rate shall be 2: 273,900 GPM when using the precision heat balance method and 2:274,800 GPM when using the elbow tap method.
This concentration bounds the condition of kerr~ 0.95 (all rods in less the most reactive rod) and subcriticality @!!rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.
Page 5 of 15
... This record was final approved on 12/20/20171 :10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 2017 Table 1 F Q(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWD/MTU)
Factor 0
1.0527 150 1.0527 354 1.0583 559 1.0652 763 1.0696 968 1.0705 1172 1.0685 1377 1.0645 1581 1.0563 1786 1.0461 1990 1.0371 2194 1.0302 2399 1.0248 2603 1.0200 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 1.0200 shall be used.
Page 6 of 15
- This record was final approved on 12120/2017 1:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 2017 Table2 Reactor Trip System Instrumentation-Overtemperature ~T (OT~T)
Setpoint Parameter Values T' $; 577.2°F Kt = 1.17 t1 :2:30 sec t4= 0 sec ft(M) =
P' = 2235 psig K2= 0.017;oF 1<3 = 0.000825/psi t2$; 4 sec ts $; 6 sec
-2.48 {23 + (qt-qb)}
0% ofRTP 2.05 {(qt-qb) -15}
t6$;6sec when (qt-qb) $; -23% RTP when -23% RTP < (qt -qb) $; 15% RTP when (qt-qb) > 15% RTP Page 7 of 15
- This record was final approved on 12/20/20171 :10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 2017 Table3 Reactor Trip System Instrumentation-Overpower L\\T (OPL\\T)
Setpoint Parameter Values T" :::; 577.2°F 1<4= 1.10
'!3 2! 10 sec t4= 0 sec ts:::; 6 sec
'!6:::; 6 sec Ks = 0.02;oF for increasing T avg Ks = 0/°F for decreasing Tavg h(L\\I) = 0% RTP for alll\\1 1<6 = 0.00109 ;oF when T > T" 1<6 = o;oF when T:::; T" Page 8 of 15
- This record was final approved on 12/20/2017 1:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 Axial Elevation Point (feet) 1 12 00 2
11.80 3
1160 4
1140 5
II 20 6
11.00 7
10 80 8
1060 9
1040 10 10 20 11 1000 12 9 80 13 960 14 9.40 15 9.20 16 9 00 17 8.80 18 8 60 19 8 40 20 8 20 21 8 00 22 7.80 23 760 24 740 25 7.20 26 700 27 6 80 28 6 60 29 640 30 620 31 6 00 32 5 80 33 5 60 34 5 40 35 5 20 36 5.00 37 4 80 38 4 60 39 4 40 40 4.20 41 4.00 42 3 80 43 3 60 44 3 40 45 3 20 46 3 00 47 2 80 48 2 60 49 2 40 so 2 20 51 2.00 52 I 80 53 160 54 I 40 55 I 20 56 1.00 57 0.80 58 0 60 59 0.40 60 0.20 61 000 150 MWD/MTU 1.0000 I 0000 I 0000 I 0000 I 0000 I 1622 I 1615 I 1574 I 1532 I 1484 1.1431 Ll464 I 1479 I 1471 I 1448 I 1414 I 1354 11337 I 1430 I 1523 I 1600 I 1660 I 1695 I 1718 I 1720 1.1716 1.1704 I 1675 I 1639 1.1597 I 1545 I 1482 I 1413 I 1332 Ll319 I 1411 I 1486 I 1560 Ll627 1.1684 I 1732 I 1772 1.1816 Ll869 I 1911 1.1989 1.2130 I 2279 I 2516 I 2779 1.3038 I 3295 I 3539 1.3771 1.3990 14191 I 0000 I 0000 1.0000 1.0000 1.0000 Table 4 RAOCW{Z) 4000 6000 MWD/MTU MWD/MTU 1.0000 I 0000 1.0000 I 0000 I 0000 I 0000 1.0000 I 0000 1.0000 l.OOOO Ll426 I 1854 I 1451 I 1874 Ll433 I 1858 Ll422 I 1839 I 1399 I 1806 I 1360 1.1756 1.1315 I 1739 1.1273 I 1768 I 1249 I 1729 Ll223 Ll732 1.1317 I 1709 Ll457 I 1670 I 1574 I 1696 I 1675 I 1798 I 1758 I 1868 1.1820 I 1919 1.1863 I 1951 I 1881 I 1959 I 1885 1.1955 1.1863 Ll923 1.1824 I 1884 I 1773 1.1837 I 1706 I 1774 1.1628 I 1699 1.1543 I 1616 I 1448 1.1524 I 1346 1.1425 I 1252 I 1317 I 1307 I 1219 I 1416 1.1260 I 1516 I 1316 I 1612 I 1370 1.1702 I 1417 1.1785 I 1459 I 1858 I 1494 I 1923 I 1522 I 1979 1.1556 I 2026 I 1592 I 2064 1.1621 I 2088 1.1637 I 2145 1.1754 1.2344 I 1972 1.2633 I 2205 I 2929 1.2437 1.3229 1.2673 1.3528 I 2905 I 3823 I 3134 I 4102 I 3353 1.4367 1.3562 1.4613 I 3757 1.4836 I 3935 I 0000 1.0000 1.0000 I 0000 I 0000 1.0000 1.0000 1.0000 1.0000 I 0000 10000 MWD/MTU I 0000 I 0000 I 0000 1.0000 I 0000 I 2647 12616 I 2555 I 2487 I 2414 I 2334 I 2262 I 2306 1.2287 I 2350 I 2380 I 2369 I 2398 I 2508 I 2580 I 2625 I 2646 I 2639 I 2616 1.2553 I 2476 1.2392 I 2289 12170 I 2037 1.1893 I 1743 I 1584 1.1484 I 1479 I 1474 I 1471 I 1457 1.1434 I 1404 I 1362 I 1332 1.1317 I 1296 I 1265 1.1246 1.1234 1.1270 1.1377 1.1495 I 1603 I 1710 I 1817 I 1924 I 2027 1.2126 I 0000 I 0000 1.0000 1.0000 I 0000 Top and bottom 5 axial points excluded per Technical Specification 83.2.1.
December 2017 14000 18000 MWD/MTU MWD/MTU I 0000 I 0000 I 0000 1.0000 I 0000 1.0000 I 0000 I 0000 I 0000 1.0000 I 2321 1.2294 I 2373 I 2286 I 2287 I 2228 1.2223 1.2168 1.2140 I 2113 I 2124 I 2060 I 2099 I 2002 I 2065 I 1940 I 2024 I 1886 I 2010 I 1911 I 2107 I 2081 I 2138 I 2313 I 2175 I 2507 I 2288 I 2688 I 2429 I 2878 I 2535 I 3036 I 2617 I 3162 I 2670 I 3253 I 2707 I 3323 I 2702 1.3339 1.2672 I 3317 I 2637 I 3274 I 2582 I 3206 I 2506 I 3110 1.2411 I 2988 I 2302 I 2849 I 2181 1.2696 I 2050 I 2520 1.1998 1.2332 I 1971 1.2304 I 1929 I 2270 I 1882 I 2243 1.1842 I 2194 I 1789 I 2127 I 1724 I 2045 I 1649 I 1948 I 1548 1.1822 1.1453 1.1671 I 1389 I 1513 I 1320 I 1366 I 1298 I 1245 I 1304 I 1227 I 1313 1.1346 I 1360 I 1493 I 1466 I 1635 I 1568 I 1763 I 1665 I 1884 I 1766 I 2009 1.1869 I 2138 1.1971 I 2266 I 2073 I 2394 1.0000 I 0000 1.0000 1.0000 I 0000 1.0000 I 0000 1.0000 1.0000 1.0000 Page 9 of 15
- This record was final approved on 12/20/20171:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 December 20 I7 Table 5 Part Power (48%) RAOC W(Z)
Axial Point Elevation (feet) lSOMWD/MTU 1
12 00 10000 2
11.80 1 0000 3
1160 1.0000 4
11 40 10000 5
ll 20 1 0000 6
1100 1 2174 7
10 80 1.2049 8
10.60 1.1924 9
10.40 1 1783 10 10 20 1 1590 11 10.00 1 1410 12 9 80 1.1286 13 9 60 1 1135 14 9.40 1 0987 15 9 20 1 0857 16 900 1 0722 17 8 80 1 0541 18 8 60 1 0452 19 8 40 1.0474 20 8 20 1 0518 21 8 00 1 0549 22 7 80 1 0578 23 7 60 1 0587 24 7.40 1.0600 25 7-20 1.0608 26 7.00 1.0625 27 6 80 1.0657 28 6 60 1.0654 29 6.40 1 0646 30 6 20 1 0668 31 6 00 1 0656 32 5 80 1 0622 33 5 60 1 0578 34 5.40 1 0586 35 5 20 1 0640 36 5 00 1.0788 37 4.80 I 0921 38 4 60 I 1055 39 4 40 1 1179 40 4 20 I 1295 41 4 00 I 1402 42 3 80 I 1516 43 3.60 I 1636 44 3 40 1.1765 45 3 20 I 1884 46 3 00 1 2034 47 2 80 I 2250 48 260 12472 49 2 40 1.2787 50 2.20 I 3131 51 2 00 1 3482 52 I 80 1.3831 53 160 14170 54 1.40 14478 55 120 1 4742 56 I 00 1.5005 57 0.80 I 0000 58 0.60 I 0000 59 040 1.0000 60 0.20 I 0000 61 0 00 I 0000 Top and bottom 5 axial points excluded per Technical Specification 83.2.1.
Page IO of IS
- This record was final approved on 12/20/20171:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29
--=
225 200 175
~ 150 E
"C
.c -
=:
~ 125 11.1 -
~
c
.S!
- "5; 100 Q
=-
..:.!: c
~ =
"C ci!
75 50 25 0
1.1" II'
~
I (0, 114)
II'
~
0.0 0.1 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn-225 to 231 steps, inclusive
,J
(.552, 225) 1.1"
~
~
~
~
~
~
~
Banke
~
~
~
1...1'
~
~
~
~
~
~
1.1" BankO
~
~
~
~
II' l.t!l
~
!-' (.070, 0)
I I I I I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Fraction of RATED THERMAL POWER December 2017 (1, 187) -
~
~
~
~
0.9 1.0 Fully Withdrawn shall be the condition where control rods are at a position within the interval ~ 225 and
- 23 I 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 11 of 15
- This record was final approved on 12/20/2017 1:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 29 December 2017 Figure 2 K(Z)- Normalized FQ(Z) as a Function of Core Height 1.2 I.
Q..
Col =
0.8 1:11) =
I
=
Q,j
=-,
Q,j
~ =
E 0.6 I.
Q ;z I,_..,
N
~
Core Height (ft.)
K(Z) 0.000 1.000 6.000 1.000 12.000 1.000 0.4 FQ =2.50 0.2 0
0 2
4 6
8 10 12 Core Height (feet)
Page 12 of 15
- This record was final approved on 12/20/2017 1:10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT l CYCLE 29 120 110 100
...... 90
~
r--
~
~
0 80 Q,
..J
~
- 70
~
~
- c Q
60
~
~ 50
~
Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC
(-12, 100)
(+9, 100) v UNACCEPTABLE l
~
OPERATION J
\\
L V_ I ACCEPTABLE
~
OPERATION I
I
\\
December 20 17 J UNACCEPTABLE L
OPERATION f--
0
(-25, 50)
(+24, 50)
~
r..
cu :;
0 Q,
40 30 20 10 0
-60
-50
-40
-30
-20
-10 0
10 20 30 40 50 60 Axial Flux Difference (Delta I) %
Page 13 of 15
- This record was final approved on 12/20/2017 1 :10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 29 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE I 0..,
OPERATION I
r--.,
........... i"-..........
660 0...
...... i"-!'--.
!'--. i"-
............ i"-
r--.,
i"-!'--.
~
~
i"-
.......... i"-r-....
640
~
['-..
~'--....,
r--.,
['-..
X..,
...... i"-
........... ['-..
...... ['-..
~
........ ['-..
r--...
......... ['-..
t-....
~
f'-..~--,
......... ['-.. t'-....
~
~
600
........... ~
I ACCEPTABLE I
['-..
I OPERATION I
580 560 0.0 0.2 0.4 0.6 0.8 1.0 Power (Fraction of RATED THERMAL POWER)
'Q 1\\
\\
............ ""n
\\
1\\
\\
1.2 December 2017
~2425psig
--o-2235 psig
-t:r--1985 psig
-x-1825 psig Page 14 of 15
- This record was final approved on 12120/2017 1 :10:32 PM. (This statement was added by the PRIME system upon its validation)
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 29 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP
~
!2...
E u
Q.
c
-23. 5
-~ - 24. 0 u
E CIJ 0 u CIJ...
- I -e CIJ c.
E
~ - 24. 5 0 -
c;...
CIJ "0
0
~
-25. 0 16000
~
...... ~
~
...... ~
r-..........
17000 18000 19000 Cycle Burnup (MWD/MTU)
Cycle Burnup Moderator Temperature (MWD/MTU)
Coefficient (pcm/°F) 16000
-23.69 17000
-23.93 18000
-24.18 19000
-24.42 20000
-24.62 December 2017 20000 Page 15 of 15
- This record was final approved on 12/20/20171:10:32 PM. (This statement was added by the PRIME system upon its validation)