NL-16-0571, Cycle 25 Core Operating Limits Report

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Cycle 25 Core Operating Limits Report
ML16145A126
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 05/24/2016
From: Pierce C
Southern Co, Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-16-0571
Download: ML16145A126 (18)
v • d • e


Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN << \

NUCLEAR A SOUTHERN COMPANY Docket Nos.: 50-364 NL-16-0571 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 25 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 25 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

C.R. Pierce Regulatory Affairs Director CRP/RMJ

Enclosure:

Core Operating Limits Report for FNP Unit 2 Cycle 25 Version 1

U. S. Nuclear Regulatory Commission NL-16-0571 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley

Joseph M. Farley Nuclear Plant - Unit 2 Cycle 25 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 25 Version 1

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 25 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 kew~ 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 kew< 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 ~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

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 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~> 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Llklk.

2.2 SHUTDOWN MARGIN- MODES 2 (with k..f[< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keft' < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent llklk.

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

Page 2 of15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLlARO-MTC shall be less than or equal to +0. 7 x 10-4 Llk/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 Llk/k/°F at 100 percent RTP.

The EOLIAROIRTP-MTC shall be less negative than -4.3 x 10-4 Llk/k/°F.

2.3.2 The MTC Surveillance limits are:

The 300 ppm/AROIRTP-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 burnup corresponding to the measurement of300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcm/aF or (LlAFD

  • AFD Sensitivity)}

where: LlAFD 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 pcm/aF I LlAFD

      • Predictive Correction is -3 pcm/°F.

The 100 ppm/AROIRTP-MTC should be less negative than -4.0 x 10-4 Llk/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.

I Page 3 ofl5

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 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)

F',RTP 2.6.1 F0 (Z) ~-Q-*K(Z) forP> 0.5

- p F',RTP F0 (Z) ~ _Q_

  • K(Z) for P ~ 0.5

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

RATEDTHERMALPOWER 2.6.2 F~TP =2.50 2.6.3 K(Z) is provided in Figure 2.

F,RTP *K(Z) 2.6.4 F. (Z) < ---'Q=---- forP> 0.5 Q - P*W(Z)

F,RTP *K(Z)

F. (Z)<-Q~-- forP ~ 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 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F:'n (Specification 3.2.2) 2.7.1 F! =:;F!'P*(l+PF/)J{ *(1-P))

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

RATED THERMAL POWER 2.7.2 2.7.3 PF/)J{ = 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) 2.10.1 In MODES 1 and 2, the combination ofTHERMAL 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 (OT~T) and Overpower ~T (OP~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 ofkeff~ 0.95 (all rods in less the most reactive rod) and subcriticality (illl rods out) over the entire cycle. Thi! concentration includes additional boron to address uncertainties and B 10 depletion. I Page 5 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Tablel F Q(Z) Penalty Factor Cycle Burnup F Q(Z) Penalty (MWDIMTU) Factor 30 1.0206 150 1.0206 354 1.0200 5668 1.0200 5872 1.0254 6077 1.0290 6281 1.0276 6485 1.0255 6690 1.0238 6894 1.0257 7098 1.0218 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 1.0200 shall be used.

Page 6 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Table2 Reactor Trip System Instrumentation- Overtemperature AT (OTAT)

Setpoint Parameter Values P' = 2235 psig K1 = 1.17 Kz = 0.017;oF 1<3 = 0.000825/psi 1:1 :2:30 sec ,;z:=;; 4 sec 1:4= 0 sec -rs::;; 6 sec ,;6:::; 6 sec h(M)= -2.48 {23 + (qt- qb)} when (qt- qb):::;; -23% R1P 0% ofR1P when -23% RTP < (qt -qb) :::;; 15% RTP 2.05 {(qt- qb) -15} when (qt- qb) > 15% R1P Page 7 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Table3 Reactor Trip System Instrumentation- Overpower AT (OPAT)

Setpoint Parameter Values 1<4= 1.10 Ks = 0.02;oF for increasing Tavg 1<6 = 0.00109/°F when T > T" Ks = 0;oF for decreasing Tavg 1<6 = o;oF when T s.; T"

't3~ 10 sec 1:4= 0 sec

-rss.; 6 sec

't6s.; 6 sec 6(Lll} = 0% RlP for all ill Page 8 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Table 4 RAOCW(Z)

Axial Point Elevation (feet) 150MWDIMTU 4000 MWDIMTU 10000 MWD/MTU 14000 MWDIMTU 18000 MWD/MTU

  • 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 11.80 1.0000 1.0000 1.0000 1.0000 1.0000 3 11.60 1.0000 1.0000 1.0000 1.0000 1.0000
  • 4 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 5 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.00 1.1307 1.1469 1.2528 1.2222 1.2204 7 10.80 1.1283 1.1481 1.2496 1.2174 1.2166 8 10.60 1.1244 1.1441 1.2440 1.2055 1.2117 9 10.40 1.1229 1.1521 1.2375 1.1992 1.2061 10 10.20 1.1229 1.1609 1.2306 1.1984 1.2010 11 10.00 1.1214 1.1672 1.2230 1.1976 1.1960 12 9.80 1.1195 1.1699 1.2179 1.1960 1.1905 13 9.60 1.1172 1.1689 1.2199 1.1934 1.1884 14 9.40 1.1144 1.1658 1.2163 1.1901 1.1883 15 9.20 1.1234 1.1586 1.2232 1.1898 1.1914 16 9.00 1.1354 1.1588 1.2262 1.2000 1.2155 17 8.80 1.1433 1.1541 1.2261 1.2037 1.2321 18 8.60 1.1519 1.1549 12296 1.2087 1.2461 19 8.40 1.1638 1.1658 1.2402 1.2213 1.2606 20 820 1.1739 1.1738 1.2471 1.2348 1.2798 21 8.00 1.1821 1.1800 1.2514 1.2453 1.2957 22 7.80 1.1882 1.1842 1.2535 1.2533 1.3084 23 7.60 1.1914 1.1858 1.2528 1.2585 1.3176 24 7.40 1.1931 1.1860 1.2505 1.2621 1.3248 25 7.20 1.1924 1.1837 1.2444 1.2616 1.3267 26 7.00 1.1902 1.1797 1.2371 1.2588 1.3250 27 6.80 1.1865 1.1745 1.2292 1.2555 1.3211 28 6.60 1.1808 1.1676 1.2194 1.2502 1.3148 29 6.40 1.1743 1.1599 1.2080 1.2430 1.3058 30 6.20 1.1671 1.1513 1.1954 1.2339 1.2942 31 6.00 1.1588 1.1419 1.1819 1.2234 1.2808 32 5.80 1.1495 1.1338 1.1739 1.2118 1.2660 33 5.60 1.1393 1.1300 1.1651 1.1994 1.2490 34 5.40 1.1298 1.1275 1.1542 1.1955 1.2308 35 5.20 1.1395 1.1362 11487 1.1933 1.2297 36 5.00 1.1481 1.1451 1.1473 1.1896 1.2252 37 4.80 1.1574 1.1537 1.1474 11855 1.2203 38 4.60 1.1661 1.1617 1.1465 1.1823 1.2156 39 4.40 1.1743 1.1692 1.1448 1.1777 1.2096 40 4.20 1.1814 1.1758 1.1422 1.1720 1.2021 41 4.00 1.1876 1.1816 1.1390 1.1652 1.1933 42 3.80 1.1933 1.1865 1.1343 1.1563 1.1816 43 3.60 1.1981 1.1906 1.1283 1.1459 I 1676 44 3.40 1.2020 1.1933 1.1218 1.1347 1.1529 45 3_20 1.2056 1.1988 1.1167 1.1256 1.1395 46 3.00 1.2157 1.2073 1.1144 1.1188 1.125 I 47 2.80 1.2277 1.2281 1.1187 1.1184 1.1281 48 2.60 1.2429 1.2563 1.1296 1.1276 1.1390 49 2_40 1.2657 1.2844 1.1411 1.1389 1.1518 so 2.20 1.2904 1.3130 1.1527 1.1499 1.1654 51 2.00 1.3148 1.3413 11635 1.1598 11774 52 1.80 1.3389 1.3693 1.1741 1.1694 1.1887 53 1.60 1.3616 1.3956 1.1847 1.1792 1.2005 54 1.40 1.3830 1.4204 11951 1.1893 1.2127 55 1.20 1.4029 1.4433 1.2051 1.1992 1.2247 56 1.00 1.4210 1.4638 12147 1.2090 1.2368 57 0_80 1.0000 1.0000 1.0000 1.0000 1.0000 58 0_60 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0_20 1.0000 1.0000 1.0000 1.0000 1.0000
  • 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000
  • Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

I Page 9 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 TableS Part Power (48%) RAOC W(Z)

Axial Point Elevation (feet) ISOMWDIMTU

  • 1 2

3 12.00 11.80 11.60 1.0000 1.0000 1.0000

  • 4 ll.40 1.0000
  • 5 11.20 1.0000 6 11.00 1.2226 7 10.80 L2079 8 10.60 1.1916 9 1040 1.1774 10 10.20 1.1626 11 10.00 1.1454 12 9.80 1.1240 13 9.60 Ll027 14 9.40 1.0837 15 9.20 1.0787 16 9.00 1.0773 17 8.80 1.0741 18 8.60 1.0740 19 8.40 1.0774 20 8.20 1.0874 21 8.00 1.0855 22 7.80 1.0878 23 7.60 L0881 24 7.40 1.0884 25 7.20 1.0862 26 7.00 1.0834 27 6.80 1.0817 28 6.60 1.0789 29 6.40 1.0764 30 6.20 L0729 31 6.00 1.0689 32 5.80 1.0644 33 5.60 1.0598 34 5.40 1.0566 35 5.20 1.0713 36 5.00 1.0852 37 4.80 I 0999 38 4.60 Lll43 39 4.40 1.1282 40 4.20 Ll413 41 4.00 Ll532 42 3.80 Ll656 43 3.60 1.1774 44 3.40 1.1888 45 3.20 1.1999 46 3.00 1.2175 47 2.80 1.2370 48 2.60 1.2585 49 2.40 1.2884 50 2.20 1.3214 51 2.00 1.3541 52 1.80 1.3862 53 1.60 1.4173 54 140 1.4472 55 1.20 l.47SS 56 1.00 1.5016
  • 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

Page 10 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn- 225 to 231 steps, inclusive 225 I I-" (.552, 225) 1.1 If" 200

' If" 1.1 "' {1,187) _

,.., 1.1 175 1.1 ~

~

c~

150 1.1 BankC I! If"

'a i .., "'

3: , 1.1 ~ "'

s"'

a. 125

~ ~

c (0, 114) ~

0 ~

+I

'iii 100 0

ll.

~ BankO c

m ..,

Ill

'a 0 75 a:

50 ,1.1

~

25 If"

~

~

~ (.070, 0)

I 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

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 11 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figurel K(Z) -Normalized FQ(Z) as a Function of Core Height 1.2 1

...0 t) cu 0.8 LL CJ c

s2 cu Cl) a.

'C Cl)

.!:::! 0.6 n;

...E0 Core Height (ft.) K(Z) 0.000 1.000 z

6.000 1.000 12.000 1.000 N

~ 0.4 FQ= 2.50 0.2 0

0 2 4 6 8 10 12 Core Height (feet)

Page 12 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110

(-12, 100) (+9, 100) v 100 90 UNACCEPTABLE '~ I UNACCEPTABLE -

\

!--i OPERATIOf t OPE tAIION 2w I

Il

~ so

\

0 a.

.... ACCEPTABLE

< 70 OP:RATIO~

\

~

I a:

w

z:

v 1- 1\

1\

cw 60

...5 50 e...

0

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

Cll 40 3:0 a.

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 IS

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE I 660 1().,

j"--... ........

OPERATION I lo...

j"--...

~

'r-.. "'

1"'-..

640 r-...

j"--...

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

r..... ~

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

........ ....... \ -v-- 2425 pslg lx... ...... ........

["r.....

........ ........ \ -o- 2235 pslg b..

r-......

...... t"-....

["r.....

~ \ -~1985pslg

-x-1825 pslg j"--...

r...... i'- r...... ~

........ ...... \

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

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

t-.....

600 ........

1"'-.. .......... i'- r.....

i'- ........

I ACCEPTABLE I r-... ..........

I OPERATION I ...... """-:

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

Page 14 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-24.0

+I f' ~

s:: .......

GJ

  • a-24.5 r-.....

...... ~

~

  • ri fl..!

fl..!

GJ 0

u ~

GJ 1-l r-.... .....

ilIll ~ :-....

! ~

-25.0

["'.

r-...

1-l B Ill

~

~

-25.5 17000 1800 0 19000 20000 21000 Cycle Burnup (MWD/MTU)

Cycle Bumup Moderator Temperature (MWD/MTU) Coefficient (pcm/°F) 17000 -24.22 18000 -24.43 19000 -24.63 20000 -24.83 21000 -25.02 Page 15 of 15

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN << \

NUCLEAR A SOUTHERN COMPANY Docket Nos.: 50-364 NL-16-0571 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 25 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 25 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

C.R. Pierce Regulatory Affairs Director CRP/RMJ

Enclosure:

Core Operating Limits Report for FNP Unit 2 Cycle 25 Version 1

U. S. Nuclear Regulatory Commission NL-16-0571 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley

Joseph M. Farley Nuclear Plant - Unit 2 Cycle 25 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 25 Version 1

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 25 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 kew~ 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 kew< 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 ~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

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 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~> 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Llklk.

2.2 SHUTDOWN MARGIN- MODES 2 (with k..f[< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keft' < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent llklk.

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

Page 2 of15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLlARO-MTC shall be less than or equal to +0. 7 x 10-4 Llk/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 Llk/k/°F at 100 percent RTP.

The EOLIAROIRTP-MTC shall be less negative than -4.3 x 10-4 Llk/k/°F.

2.3.2 The MTC Surveillance limits are:

The 300 ppm/AROIRTP-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 burnup corresponding to the measurement of300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcm/aF or (LlAFD

  • AFD Sensitivity)}

where: LlAFD 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 pcm/aF I LlAFD

      • Predictive Correction is -3 pcm/°F.

The 100 ppm/AROIRTP-MTC should be less negative than -4.0 x 10-4 Llk/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.

I Page 3 ofl5

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 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)

F',RTP 2.6.1 F0 (Z) ~-Q-*K(Z) forP> 0.5

- p F',RTP F0 (Z) ~ _Q_

  • K(Z) for P ~ 0.5

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

RATEDTHERMALPOWER 2.6.2 F~TP =2.50 2.6.3 K(Z) is provided in Figure 2.

F,RTP *K(Z) 2.6.4 F. (Z) < ---'Q=---- forP> 0.5 Q - P*W(Z)

F,RTP *K(Z)

F. (Z)<-Q~-- forP ~ 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 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F:'n (Specification 3.2.2) 2.7.1 F! =:;F!'P*(l+PF/)J{ *(1-P))

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

RATED THERMAL POWER 2.7.2 2.7.3 PF/)J{ = 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) 2.10.1 In MODES 1 and 2, the combination ofTHERMAL 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 (OT~T) and Overpower ~T (OP~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 ofkeff~ 0.95 (all rods in less the most reactive rod) and subcriticality (illl rods out) over the entire cycle. Thi! concentration includes additional boron to address uncertainties and B 10 depletion. I Page 5 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Tablel F Q(Z) Penalty Factor Cycle Burnup F Q(Z) Penalty (MWDIMTU) Factor 30 1.0206 150 1.0206 354 1.0200 5668 1.0200 5872 1.0254 6077 1.0290 6281 1.0276 6485 1.0255 6690 1.0238 6894 1.0257 7098 1.0218 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 1.0200 shall be used.

Page 6 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Table2 Reactor Trip System Instrumentation- Overtemperature AT (OTAT)

Setpoint Parameter Values P' = 2235 psig K1 = 1.17 Kz = 0.017;oF 1<3 = 0.000825/psi 1:1 :2:30 sec ,;z:=;; 4 sec 1:4= 0 sec -rs::;; 6 sec ,;6:::; 6 sec h(M)= -2.48 {23 + (qt- qb)} when (qt- qb):::;; -23% R1P 0% ofR1P when -23% RTP < (qt -qb) :::;; 15% RTP 2.05 {(qt- qb) -15} when (qt- qb) > 15% R1P Page 7 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Table3 Reactor Trip System Instrumentation- Overpower AT (OPAT)

Setpoint Parameter Values 1<4= 1.10 Ks = 0.02;oF for increasing Tavg 1<6 = 0.00109/°F when T > T" Ks = 0;oF for decreasing Tavg 1<6 = o;oF when T s.; T"

't3~ 10 sec 1:4= 0 sec

-rss.; 6 sec

't6s.; 6 sec 6(Lll} = 0% RlP for all ill Page 8 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Table 4 RAOCW(Z)

Axial Point Elevation (feet) 150MWDIMTU 4000 MWDIMTU 10000 MWD/MTU 14000 MWDIMTU 18000 MWD/MTU

  • 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 11.80 1.0000 1.0000 1.0000 1.0000 1.0000 3 11.60 1.0000 1.0000 1.0000 1.0000 1.0000
  • 4 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 5 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.00 1.1307 1.1469 1.2528 1.2222 1.2204 7 10.80 1.1283 1.1481 1.2496 1.2174 1.2166 8 10.60 1.1244 1.1441 1.2440 1.2055 1.2117 9 10.40 1.1229 1.1521 1.2375 1.1992 1.2061 10 10.20 1.1229 1.1609 1.2306 1.1984 1.2010 11 10.00 1.1214 1.1672 1.2230 1.1976 1.1960 12 9.80 1.1195 1.1699 1.2179 1.1960 1.1905 13 9.60 1.1172 1.1689 1.2199 1.1934 1.1884 14 9.40 1.1144 1.1658 1.2163 1.1901 1.1883 15 9.20 1.1234 1.1586 1.2232 1.1898 1.1914 16 9.00 1.1354 1.1588 1.2262 1.2000 1.2155 17 8.80 1.1433 1.1541 1.2261 1.2037 1.2321 18 8.60 1.1519 1.1549 12296 1.2087 1.2461 19 8.40 1.1638 1.1658 1.2402 1.2213 1.2606 20 820 1.1739 1.1738 1.2471 1.2348 1.2798 21 8.00 1.1821 1.1800 1.2514 1.2453 1.2957 22 7.80 1.1882 1.1842 1.2535 1.2533 1.3084 23 7.60 1.1914 1.1858 1.2528 1.2585 1.3176 24 7.40 1.1931 1.1860 1.2505 1.2621 1.3248 25 7.20 1.1924 1.1837 1.2444 1.2616 1.3267 26 7.00 1.1902 1.1797 1.2371 1.2588 1.3250 27 6.80 1.1865 1.1745 1.2292 1.2555 1.3211 28 6.60 1.1808 1.1676 1.2194 1.2502 1.3148 29 6.40 1.1743 1.1599 1.2080 1.2430 1.3058 30 6.20 1.1671 1.1513 1.1954 1.2339 1.2942 31 6.00 1.1588 1.1419 1.1819 1.2234 1.2808 32 5.80 1.1495 1.1338 1.1739 1.2118 1.2660 33 5.60 1.1393 1.1300 1.1651 1.1994 1.2490 34 5.40 1.1298 1.1275 1.1542 1.1955 1.2308 35 5.20 1.1395 1.1362 11487 1.1933 1.2297 36 5.00 1.1481 1.1451 1.1473 1.1896 1.2252 37 4.80 1.1574 1.1537 1.1474 11855 1.2203 38 4.60 1.1661 1.1617 1.1465 1.1823 1.2156 39 4.40 1.1743 1.1692 1.1448 1.1777 1.2096 40 4.20 1.1814 1.1758 1.1422 1.1720 1.2021 41 4.00 1.1876 1.1816 1.1390 1.1652 1.1933 42 3.80 1.1933 1.1865 1.1343 1.1563 1.1816 43 3.60 1.1981 1.1906 1.1283 1.1459 I 1676 44 3.40 1.2020 1.1933 1.1218 1.1347 1.1529 45 3_20 1.2056 1.1988 1.1167 1.1256 1.1395 46 3.00 1.2157 1.2073 1.1144 1.1188 1.125 I 47 2.80 1.2277 1.2281 1.1187 1.1184 1.1281 48 2.60 1.2429 1.2563 1.1296 1.1276 1.1390 49 2_40 1.2657 1.2844 1.1411 1.1389 1.1518 so 2.20 1.2904 1.3130 1.1527 1.1499 1.1654 51 2.00 1.3148 1.3413 11635 1.1598 11774 52 1.80 1.3389 1.3693 1.1741 1.1694 1.1887 53 1.60 1.3616 1.3956 1.1847 1.1792 1.2005 54 1.40 1.3830 1.4204 11951 1.1893 1.2127 55 1.20 1.4029 1.4433 1.2051 1.1992 1.2247 56 1.00 1.4210 1.4638 12147 1.2090 1.2368 57 0_80 1.0000 1.0000 1.0000 1.0000 1.0000 58 0_60 1.0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0_20 1.0000 1.0000 1.0000 1.0000 1.0000
  • 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000
  • Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

I Page 9 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 TableS Part Power (48%) RAOC W(Z)

Axial Point Elevation (feet) ISOMWDIMTU

  • 1 2

3 12.00 11.80 11.60 1.0000 1.0000 1.0000

  • 4 ll.40 1.0000
  • 5 11.20 1.0000 6 11.00 1.2226 7 10.80 L2079 8 10.60 1.1916 9 1040 1.1774 10 10.20 1.1626 11 10.00 1.1454 12 9.80 1.1240 13 9.60 Ll027 14 9.40 1.0837 15 9.20 1.0787 16 9.00 1.0773 17 8.80 1.0741 18 8.60 1.0740 19 8.40 1.0774 20 8.20 1.0874 21 8.00 1.0855 22 7.80 1.0878 23 7.60 L0881 24 7.40 1.0884 25 7.20 1.0862 26 7.00 1.0834 27 6.80 1.0817 28 6.60 1.0789 29 6.40 1.0764 30 6.20 L0729 31 6.00 1.0689 32 5.80 1.0644 33 5.60 1.0598 34 5.40 1.0566 35 5.20 1.0713 36 5.00 1.0852 37 4.80 I 0999 38 4.60 Lll43 39 4.40 1.1282 40 4.20 Ll413 41 4.00 Ll532 42 3.80 Ll656 43 3.60 1.1774 44 3.40 1.1888 45 3.20 1.1999 46 3.00 1.2175 47 2.80 1.2370 48 2.60 1.2585 49 2.40 1.2884 50 2.20 1.3214 51 2.00 1.3541 52 1.80 1.3862 53 1.60 1.4173 54 140 1.4472 55 1.20 l.47SS 56 1.00 1.5016
  • 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

Page 10 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn- 225 to 231 steps, inclusive 225 I I-" (.552, 225) 1.1 If" 200

' If" 1.1 "' {1,187) _

,.., 1.1 175 1.1 ~

~

c~

150 1.1 BankC I! If"

'a i .., "'

3: , 1.1 ~ "'

s"'

a. 125

~ ~

c (0, 114) ~

0 ~

+I

'iii 100 0

ll.

~ BankO c

m ..,

Ill

'a 0 75 a:

50 ,1.1

~

25 If"

~

~

~ (.070, 0)

I 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

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 11 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figurel K(Z) -Normalized FQ(Z) as a Function of Core Height 1.2 1

...0 t) cu 0.8 LL CJ c

s2 cu Cl) a.

'C Cl)

.!:::! 0.6 n;

...E0 Core Height (ft.) K(Z) 0.000 1.000 z

6.000 1.000 12.000 1.000 N

~ 0.4 FQ= 2.50 0.2 0

0 2 4 6 8 10 12 Core Height (feet)

Page 12 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110

(-12, 100) (+9, 100) v 100 90 UNACCEPTABLE '~ I UNACCEPTABLE -

\

!--i OPERATIOf t OPE tAIION 2w I

Il

~ so

\

0 a.

.... ACCEPTABLE

< 70 OP:RATIO~

\

~

I a:

w

z:

v 1- 1\

1\

cw 60

...5 50 e...

0

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

Cll 40 3:0 a.

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 IS

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE I 660 1().,

j"--... ........

OPERATION I lo...

j"--...

~

'r-.. "'

1"'-..

640 r-...

j"--...

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

r..... ~

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

........ ....... \ -v-- 2425 pslg lx... ...... ........

["r.....

........ ........ \ -o- 2235 pslg b..

r-......

...... t"-....

["r.....

~ \ -~1985pslg

-x-1825 pslg j"--...

r...... i'- r...... ~

........ ...... \

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

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

t-.....

600 ........

1"'-.. .......... i'- r.....

i'- ........

I ACCEPTABLE I r-... ..........

I OPERATION I ...... """-:

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

Page 14 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 25 JANUARY 2016 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-24.0

+I f' ~

s:: .......

GJ

  • a-24.5 r-.....

...... ~

~

  • ri fl..!

fl..!

GJ 0

u ~

GJ 1-l r-.... .....

ilIll ~ :-....

! ~

-25.0

["'.

r-...

1-l B Ill

~

~

-25.5 17000 1800 0 19000 20000 21000 Cycle Burnup (MWD/MTU)

Cycle Bumup Moderator Temperature (MWD/MTU) Coefficient (pcm/°F) 17000 -24.22 18000 -24.43 19000 -24.63 20000 -24.83 21000 -25.02 Page 15 of 15

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