NL-19-0565, Submittal of Cycle 27 Core Operating Limits Report

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Submittal of Cycle 27 Core Operating Limits Report
ML19151A771
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 05/31/2019
From: Wheat J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-19-0565
Download: ML19151A771 (18)
v • d • e


Text

~ Southern Nuclear Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 tel 205 992 7795 fax MAY 3 1 2019 Docket No.: 50-364 NL-19-0565 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 27 Core Operating Limits Report Ladies and Gentlemen:

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 2 Cycle 27 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.

Respectfully submitted, Justin T. Wheat Licensing Manager JTW/was/scm

Enclosure:

Core Operating Limits Report for FNP Unit 2 Cycle 27 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 2 Cycle 27 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 27 Version 1

SOUTHERN COMPANY A.

Energy to Serve Your World" Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 27 Version 1 January 2019

      • This record was final approved on 2/8/2019 4:11:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 27 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 1 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 kerr< 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 .1T (OT.1T) and Overpower .1T (OP.1T) Setpoint Parameter Values for Table 3.3.1-1 3.4. I RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration Page I of 15

      • This record was final approved on 218/2019 4:01:1018 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 2.0 OPERATfNG 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..ff 2::: 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ilklk.

2.2 SHUTDOWN MARGIN- MODES 2 (with k..rr< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (ketr < 1.0), 3 and 4- The SHUTDOWN MARGIN shall be greater than or equal to I. 77 percent ilklk.

2.2.2 Mode 5 -The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent ilk/k.

Page 2 of 15

      • This record was final approved on 2/8/2019 4:01:1:!8 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 20 19 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 ilk/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 ilk!k/°F at 100 percent RTP.

The EOLIARO/RTP-MTC shall be less negative than -4.3 x 10-4 ilklk/°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 10-4 Llk/k/°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 bumup corresponding to the measurement of 300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcm/°F or (LlAFD

  • AFD Sensitivity)}

where: ilAFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the bumup corresponding to 300 ppm, AFD Sensitivity = 0.07 pcm/°F I ilAFD

      • Predictive Correction is -3 pcm/°F.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 10-4 ilk!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 3.1.5) 2.4.1 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 218/2019 4:03:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 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) for P> 0.5 Filii' F0 (Z) ~ _Q_* K(Z) for P ~ 0.5

- 0.5 THERMAL POWER where: p =----------

RATED THERMAL POWER 2.6.2 F~ ' =2.50 111 2.6.3 K(Z) is provided in Figure 2.

F01171'

  • K(Z) 2.6.4 F (Z) < - =--- - - for P> 0.5 Q - P*W(Z)

F 11111' *K(Z)

F (Z) < _c=-- - - for P ~ 0.5 Q - 0.5*W(Z) 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 of15

      • This record was final approved on 2/B/2019 4:01:98 PM . (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F; (Specification 3.2.2) 2.7.1 FN w- < FtJ.H 111

~' * (I+ PFw *(I- P))

THERMAL POWER where: p =----------

RATED THERMAL POWER 2.7.2 F/:// = 1.70 2.7.3 PFMI =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 ~T COT~T) and Overpower ~T COP~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 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~ 2209 psig;
b. RCS average temperature~ 580.3°F; and
c. The minimum RCS total flow rate shall be~ 273,900 GPM when using the precision heat balance method and~ 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 (all 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 2/8/2019 4:0Ul8 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 Tablet F o(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWD/MTU) Factor 150 1.0220 354 1.0297 559 1.0346 763 1.0366 968 1.0357 1172 1.0321 1377 1.0268 1581 1.0209 1785 1.0200 10780 1.0200 10985 1.0203 11189 1.0212 11394 1.0222 11598 1.0233 11803 1.0245 12007 1.0258 12212 1.0266 12416 1.0265 12620 1.0240 12825 1.0213 13029 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 2/8/2019 4:01:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 27 January 2019 Table2 Reactor Trip System Instrumentation- Overtemperature £\T (OT£\T)

Setpoint Parameter Values P' = 2235 psig K1 = 1.17 1<3 = 0.000825I psi t1;;::: 30 sec t2~ 4 sec t4= 0 sec ts~ 6 sec t6~ 6 sec h(£\1) = -2.48 {23 + (qt- qb)} when (qt- qb) ~ -23% RTP 0% ofRTP when -23% RTP < (qt -qb) ~ 15% RTP 2.05 {(qt- qb) -15} when (qt- qb) > 15% RTP Page 7 of 15

      • This record was final approved on 218/2019 4:01:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 Table 3 Reactor Trip System Instrumentation- Overpower ~T (OP~T)

Setpoint Parameter Values 1<4= 1.10 Ks = 0.02;aF for increasing Tavg 1<6 = 0.00109;oF when T > T" Ks = 0;oF for decreasing Tavg 1<6 = o;oF when T:::; T" t3~ 10 sec t4 = 0 sec ts:::; 6 sec t6::; 6 sec 6(~1) = 0% RTP for all ~I Page 8 of 15

      • This record was final approved on 218/2019 4:03:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 Table 4 RAOCW(Z)

Axial Elevation ISO 4000 6000 10000 14000 18000 Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • 2 11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 I 0000 4 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 I 0000 6 11.00 1.1638 1.1694 1.2048 1.2140 1.2294 I 1996 7 10.80 1.1676 1.1713 1.2064 1.2139 1.2286 1.1933 8 10.60 1.1667 1.1668 1.2015 1.2109 1.2234 1.1807 9 10.40 1.1667 1.1650 1.1991 1.2112 1.2180 I 1736 10 10.20 1.1652 1.1619 1.1956 1.2144 1.2126 I 1672 11 10.00 1.1619 1.1572 1.1905 1.2117 1.2071 1.1650 12 9.80 1.1581 1.1518 1.1847 1.2165 1.2011 I 1674 13 9.60 1.1537 1.1458 1.1866 1.2191 1.1948 I 1758 14 9.40 1.1487 1.1475 1.1808 1.2195 1.1963 1.1826 15 9.20 1.1507 1.1497 1.1817 1.2189 1.2086 1.1885 16 9.00 1.1627 1.1583 1.1799 1.2238 1.2176 1.2014 17 8.80 1.1696 1.1622 1.1749 1.2305 1.2216 1.2255 18 8.60 1.1774 1.1674 1.1774 1.2370 1.2241 1.2452 19 8.40 1.1883 1.1772 1.1887 1.2471 1.2330 1.2633 20 8.20 1.1974 1.1857 1.1964 1.2556 1.2475 I 2824 21 8.00 1.2045 1.1920 1.2021 1.2611 1.2583 1.2987 22 7.80 1.2094 1.1963 1.2058 1.2643 1.2664 I 3118 23 7.60 1.2113 1.1979 1.2069 1.2645 1.2718 1.3214 24 7.40 1.2116 1.1981 1.2066 1.2632 1.2754 1.3290 25 7.20 1.2093 1.1956 1.2034 1.2578 1.2747 1.3312 26 7.00 1.2054 1.1913 1.1994 1.2509 1.2715 1.3296 27 6.80 1.2000 1.1857 1.1945 1.2433 1.2678 I 3260 28 6.60 1.1927 1.1785 1.1879 1.2338 1.2621 I 3198 29 6.40 1.1843 1.1702 1.1800 1.2226 1.2543 1.3109 30 6 .20 1.1752 1.1610 1.1712 1.2098 1.2445 1.2993 31 6.00 1.1650 1.1508 1.1614 1.1960 1.2333 1.2860 32 5.80 1.1538 1.1400 1.1509 1.1812 1.2208 I 2713 33 5.60 1.1431 1.1284 1.1395 1.1654 1.2072 1.2542 34 5.40 1.1350 1.1215 1.1261 1.1520 1.2005 1.2341 35 5.20 1.1288 1.1298 1.1205 1.1498 1.2014 1.2315 36 5.00 1.1319 1.1377 1.1267 1.1492 1.2005 1.2282 37 4.80 1.1397 1.1459 1.1312 1.1490 1.1986 1.2260 38 4.60 1.1466 1.1535 1.1356 1.1477 1.19) I 1.2215 39 4.40 1.1531 1.1605 1.1394 1.1455 1.190 I 1.2153 40 4 20 1.1588 1.1666 1.1426 1.1426 1.1839 1.2074 41 4 00 1.1631 1.1720 1.1451 1.1414 1.1766 I 1982 42 3 80 1.1697 1.1764 1.1480 1.1405 1.1672 1.1859 43 3.60 1.1782 1.1801 1.1510 1.1378 1.1552 1.1713 44 3.40 1.1852 1.1824 1.1533 1.1346 1.1475 1.1555 45 3.20 1.1908 1.1873 1.1542 1.1309 1.1428 1.1440 46 3.00 1.1985 1.1940 1.1627 1.1292 1.1416 1.1430 47 2.80 1.2062 1.2147 1.1825 1.1365 1.1509 I 1556 48 2 60 1.2291 1.2434 1.2046 1.1487 1.1653 I 1715 49 2.40 1.2575 1.2722 1.2266 1.1605 1.1790 I 1871 50 2.20 1.2855 1.3016 1.2490 1.1726 1.1929 1.2029 51 2.00 1.3138 1.3309 1.2711 1.1840 1.2055 1.2171 52 1.80 1.3418 1.3598 1.2929 1.195 I 1.2176 1.2306 53 1.60 1.3684 1.3874 1.3138 1.2064 1.2299 1.2446 54 1.40 1.3938 1.4136 1.3337 1.2175 1.2422 I 2588 55 1.20 1.4177 1.4381 1.3525 1.2283 1.2542 1.2729 56 1.00 1.4397 1.4603 1.3697 1.2387 1.2660 1.2870
  • 57 0.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 61 000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
  • Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

Page 9 of 15

      • This record was final approved on 2/8/2019 4:CIUI8 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 Table 5 Part Power (48%) RAOC W(Z)

Axial Point Elevation (feet) 150 MWD/MTU 1 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 11.00 1.2728 7 10.80 1.2681 8 10.60 1.2550 9 10.40 1.2415 10 10.20 1.2245 II 10.00 1.2039 12 9.80 1.1794 13 9.60 1.1544 14 9.40 1.1302 15 9.20 1.1154 16 9.00 1.1117 17 8.80 1.1072 18 8.60 1.1061 19 8.40 1.1085 20 8.20 1.1118 21 8.00 1.1137 22 7.80 1.1150 23 7.60 1.1137 24 7.40 1.1128 25 7.20 1.1113 26 7.00 1.1091 27 6.80 1.1045 28 6.60 1.1004 29 6.40 1.0941 30 6.20 1.0828 31 6.00 1.0761 32 5.80 1.0721 33 5.60 1.0719 34 5.40 1.0632 35 5.20 1.0611 36 5.00 1.0699 37 4.80 1.0831 38 4.60 1.0955 39 4.40 1.1074 40 4.20 1.1188 41 4.00 1.1287 42 3.80 1.1421 43 3.60 1.1576 44 3.40 1.1716 45 3.20 1.1844 46 3.00 1.1991 47 2.80 1.2139 48 2.60 1.2436 49 2.40 1.2792 50 2.20 1.3148 51 2.00 1.3518 52 1.80 1.3883 53 1.60 1.4238 54 1.40 1.4588 55 1.20 1.4934 56 1.00 1.5247 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0 20 1.0000 61 0.00 1.0000
  • Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

Page 10 of 15

      • This record was final approved on 2/8/2019 4:03:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 27 January 2019 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225

~ (.552, 225)

~

If" 200

(1, 187) -

~

175  !.1

~

,.. Banke

,....., I..;I ..;1 c

a: ISO ~ ~

E ~

"0

.c

!.1 I..;I ..;1

~ ~ If"

~

~ 125

~ I. ;

~

~

c

.!2 1-(0, 114) ,.. ~

  • '50 100

~

Q., / Bank D c

==

"0

~

75

,II' 1.1" 50 1.1" 25 If"

..;1'

~ (.070, 0)

I I I I I 0 '

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

s; 231 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, 8, C, D and a control bank tip-to-tip distance of 128 steps.

Page II of 15

      • This record was final approved on 2/8/2019 4:01:1018 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 20 19 Figure 2 K(Z)- Normalized FQ(Z) as a Function of Core Height 1.2

....uQ

~

'- 0.8 tiD c

~

Q,j Q.,

"0 Q,j

.!::l s... 0.6 z

Q Core Height (ft.) K(Z) 0.000 1.000 N'

._, 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 2/8/2019 4 :11:118 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 27 January 2019 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110

(-12, 100) (+9, 100)

I 100 I-----1J UN ACCEPT ABLE

'~ UNACCEPTABLE a: 90 L OPERATION -

\

- OPERATION

I

~

II 0

c.. 80

..J

?! 70 a:

ACCEPTABLE OPERATION

\

\

~

E- I

\

60 Q

~

E-50 I

...~

0

(-25, 50) (+24, 50)

-:!e.

'-" 40

""'~

Cll 0

c.. 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 218/2019 4:0UI8 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 27 January 2019 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE OPERATION I

IO...

I'--. ......... I 660 ~""'-

1'"--- ...........

Ic.... I'--. ..........

1'"--- ...... ..........

I'--. .......... .....

640 .......... ..........

1'"--- ..........

r......

1'"--- .......... .......... ..........

......... r-.. ~

.......... 1'"--- r..... \ --->--- 2425 psig IX... 1'"--- ..........

1'"--- .......... ~"'--- ......... \ --o- 2235 psig

""' \

1'"--- ........... ~"'--- ......... 1'"--- -~1985 psig

.......... ....... -x-1825 psig

~"'---

r--..... 1'"--- .......... \

l 1'"--- r-..... 1'"--- ...........

1"'---r-.., ..........

600 ........

~"'--- ~ ......... .........

~"'---

I ACCEPTABLE OPERATION I .........

1'"---

I I ..... ~

580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)

Page I4 of 15

      • This record was final approved on 2/8/2019 4:11:98 PM. (This statement was added by the PRIME system upon its validation)

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 27 January 2019 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-23.5 r;

0

'El0

~

["'..

+I r:: r--.....

i""'-..

  • a (I)

-24. o i'....

  • rl ........

IH i'-.

IH i'. .....

(I) 0 u

(I) i'.

r-.... r--...

~

.Bnl

~

f"'. r-....

~ -24.5 .....

m E-t 0

+I

~

' r-.... r--...

nl

.g

~

£

-25 . 0 16000 17000 18000 19000 2 0000 Cycle Burnup (MWD/MTU)

Cycle Bumup Moderator Temperature (MWD/MTU) Coefficient ([!Cm/°F) 16000 -23.80 17000 -24.04 18000 -24.28 19000 -24.49 20000 -24.71 Page 15 of 15

      • This record was final approved on 218/2019 4:111:98 PM. (This statement was added by the PRIME system upon its validation)
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