NL-17-2053, Submittal of Cycle 26 Core Operating Limits Report

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Submittal of Cycle 26 Core Operating Limits Report
ML17346B172
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/12/2017
From: Wheat J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-2053
Download: ML17346B172 (18)
v • d • e


Text

~ Southern Nuclear December 12, 2017 Docket Nos.: 50-348 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Regulatory Affairs Joseph M. Farley Nuclear Plant-Unit 2 Cycle 26 Core Operating Limits Report Ladies and Gentlemen:

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 5000 tel 205 992 7601 fax NL-17-2053 In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLA) for the Joseph M.

Farley Nuclear Plant (FNP) - Unit 2 Cycle 26 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

Respectfully submitted, Justin T. Wheat Regulatory Affairs Manager JTW/NDJ/CJ

Enclosure:

Core Operating Limits Report for FNP Unit 2 Cycle 26 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 26 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 26 Version 1

SOUTHERN*\\

COMPANY Energy to Serve Your WOrtJ*

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 26 Version 1 July 2017

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 26 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 ketr;?: 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 ketr< 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 26 July 2017 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 Kef£ 2: 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ~k/k.

2.2 SHUTDOWN MARGIN - MODES 2 (with kerr< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (k.ff< 1.0), 3 and 4-The SHUTDOWN MARGIN shall be greater than or equal to 1. 77 percent ~k/k.

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

Page 2 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 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 104 ilk/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 ilklk/°F at 100 percent RTP.

The EOLIARO/RTP-MTC shall be less negative than -4.3 x 10'4 ilk/k/°F.

2.3.2 The MTC Surveillance limits are:

The 300 pprn/AROIRTP-MTC should be less negative than or equal to

-3.65 X 10'4 flk/k/°F.

The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5 and the following algorithm:

Revised Predicted MTC Correction***

Predicted MTC* + AFD Correction** + Predictive

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 pcrn/°F or (ilAFD

  • AFD Sensitivity)}

where: ilAFD 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 pcrn/°F I ilAFD

      • Predictive Correction is -3 pcrn/°F.

The 100 pprn/ARO/RTP-MTC should be less negative than -4.0 x 104 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

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 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 I.

2.6 Heat Flux Hot Channel Factor-FQ (Z) (Specification 3.2.1) for P > 0.5 for P :5 0.5 where:

THERMAL POWER p = ----~-----

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

2.6.4 FRTP *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 :5 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

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July2017 2.7 Nuclear Enthalpy Rise Hot Channel Factor-F~ (Specification 3.2.2) 2.7.1 F~ ~ F~P *(1+ PFMI *(1-P))

where:

THERMAL POWER p =-----------

RATED THERMAL POWER 2.7.2 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. I 0. I 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. I I Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower ~T (OP~T)

Setpoint Parameter Values for Table 3.3. I -I (Specification 3.3. I) 2.11. I The Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower

~ T (OP~ T) setpoint parameter values forTS Table 3.3. I-I are listed in COLR Tables 2 and 3.

2. I 2 RCS DNB Parameters for Pressurizer Pressure. RCS Average Temperature, and RCS Total Flow Rate (Specification 3.4. I)
2. I2. I 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 8 10 depletion.

Page 5 of IS

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 26 July 2017 Tablet FQ(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWD/MTU)

Factor 0

1.0339 150 1.0339 354 1.0298 559 1.0248 763 1.0201 968 1.0200 6282 1.0200 6487 1.0242 6691 1.0293 6896 1.0321 7100 1.0295 7304 1.0267 7509 1.0239 7713 1.0210 7918 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

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July2017 Table2 Reactor Trip System Instrumentation-Overtemperature L\\T (OTL\\T)

Setpoint Parameter Values K1 = 1.17

'tl :2:30 sec

't4 = 0 sec h(t11) =

P' = 2235 psig

-r2:S; 4 sec

-rs:S; 6 sec

-2.48 {23 + (qt-qb)}

0% ofRTP 2.05 {(qt-qb)- 15}

1<.3 = 0.000825/psi when (qt-qb) :S; -23% RTP when -23% RTP < (qt -qb) :S; 15% RTP when (qt-qb) > 15% RTP Page 7 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 Table3 Reactor Trip System Instrumentation-Overpower.dT (OP.dT)

Setpoint Parameter Values T" :::;; 577.2°F 1<4= 1.10 t3~ 10 sec t4= 0 sec ts::;; 6 sec t6=:;; 6 sec Ks = 0.02;oF for increasing Tavg Ks = o;oF for decreasing Tavg fz(~I) = 0% RTP for all ~I 1<6 = 0.00109 ;oF when T > T" K6 = o;oF when T :::;; T" Page 8 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 Axial Elevation Point (feet) 1 12.00 2

II 80 3

11.60 4

1140 5

11.20 6

II 00 7

10 80 8

10 60 9

10 40 10 10 20 11 10 00 12 9 80 13 9 60 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 7.60 24 7.40 25 7 20 26 7 00 27 6 80 28 6.60 29 6 40 30 6 20 31 6.00 32 5.80 33 5 60 34 540 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 50 2.20 51 2.00 52 I 80 53 1.60 54 1.40 55 I 20 56 1.00 57 0.80 58 0.60 59 0.40 60 0.20 61 0.00 150 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.1255 I 1254 I 1210 I 1195 I 1208 I 1302 I 1357 I 1384 I 1402 1.1384 I 1418 1.1423 I 1464 I 1590 I 1686 I 1766 1.1826 I 1859 I 1878 I 1873 I 1853 I 1819 1.1766 I 1705 I 1637 I 1558 I 1469 I 1371 I 1286 I 1357 I 1433 I 1515 I 1608 I 1693 I 1770 1.1832 I 1921 I 2031 I 2123 I 2207 I 2271 I 2415 1.2686 I 2975 I 3262 I 3548 I 3830 I 4095 1.4346 I 4579 I 4791 1.0000 I 0000 1.0000 1.0000 1.0000 Table4 RAOCW(Z) 3000 6000 MWD/MTU MWD/MTU I 0000 I 0000 I 0000 I 0000 1.0000 I 0000 1.0000 I 0000 1.0000 I 0000 1.1449 12133 I 1465 I 2117 1.1427 I 2054 1.1545 12114 1.1617 I 2177 1.1583 I 2146 I 1506 1.2077 1.1450 I 2029 I 1352 I 1918 1.1357 1.1925 I 1356 I 1904 I 1397 I 1863 I 1511 I 1885 1.1612 I 1989 I 1697 I 2058 I 1763 I 2105 1.1809 1.2133 I 1830 I 2134 I 1838 I 2121 1.1821 I 2079 I 1787 12028 I 1741 I 1969 1.1679 I 1891 I 1607 I 1802 I 1528 I 1702 1.1439 1.1594 1.1342 I 1478 I 1273 I 1353 I 1303 I 1219 1.1417 1.1227 I 1518 1.1293 1.1616 I 1350 I 1708 1.1404 I 1794 I 1451 I 1870 1.1491 I 1938 I 1525 I 1995 I 1549 12061 1.1564 I 2142 1.1573 1.2223 1.1596 I 2290 I 1679 1.2513 I 1892 1.2826 1.2141 1.3136 1.2385 I 3450 1.2634 1.3762 1.2877 1.4068 13116 I 4357 13344 1.4629 1.3560 1.4881 13761 1.5107 1.3944 1.0000 I 0000 1.0000 I 0000 1.0000 I 0000 1.0000 I 0000 1.0000 I 0000 10000 MWD/MTU I 0000 I 0000 I 0000 1.0000 1.0000 I 2457 1.2474 I 2405 1.2272 I 2148 1.2113 I 2108 I 2133 I 2165 I 2155 I 2233 I 2250 1.230 I I 2436 I 2535 1.2605 I 2649 I 2663 I 2659 1.2615 I 2545 I 2460 I 2355 I 2233 I 2095 I 1947 I 1791 I 1646 I 1577 I 1588 I 1588 I 1581 1.1563 I 1537 I 1501 I 1458 I 1397 I 1340 I 1320 I 1298 I 1312 1.1431 I 1577 I 1718 I 1863 1.1997 I 2128 I 2257 I 2382 I 2503 I 2617 1.0000 I 0000 I 0000 1.0000 I 0000 Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

July 2017 14000 18000 MWD/MTU MWD/MTU I 0000 I 0000 1.0000 1.0000 I 0000 I 0000 I 0000 I 0000 I 0000 I 0000 I 2563 I 2149 I 2540 I 2067 1.2342 1.195 I I 2216 I 1865 I 2148 I 1790 I 2081 I 1720 1.2009 1.1753 I 1934 I 1831 I 1887 I 1892 I 2009 I 1936 I 2094 I 2001 I 2128 I 2234 1.2163 I 2459 I 2279 I 2661 1.2427 I 2854 1.2540 1.3013 I 2627 I 3138 12686 I 3229 I 2727 I 3299 1.2725 1.3315 I 2699 I 3293 I 2667 I 3250 I 2615 I 3183 I 2542 I 3089 I 2449 12968 I 2341 I 2831 I 2222 I 2680 I 2087 I 2506 1.1947 1.2308 I 1930 I 2294 I 1899 I 2256 I 1877 I 2230 1.1837 I 2181 I 1785 I 2115 I 1719 I 2033 I 1657 I 1937 I 1600 I 1813 1.1530 I 1656 1.1452 I 1538 I 1374 I 1441 I 1273 I 1381 1.1339 1.1465 I 1468 I 1622 I 1587 I 1771 I 1711 I 1924 1.1822 I 2060 1.1929 I 2189 I 2040 I 2323 I 2152 1.2460 I 2262 I 2596 I 2372 I 2733 I 0000 I 0000 I 0000 I 0000 1.0000 I 0000 1.0000 I 0000 I 0000 I 0000 Page 9 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 TableS Part Power (48%) RAOC W(Z)

Axial Point Elevation (feet) 150 MWD/MTU 1

12.00 I 0000 2

II 80 I 0000 3

11.60 I 0000 4

11.40 I 0000 5

11.20 1.0000 6

11.00 I 1692 7

10.80 1.1626 8

10.60 I 1483 9

10.40 1.1372 10 10.20 I 1295 11 10.00 1.1289 12 9 80 I 1220 13 960 I 1115 14 940 I 1001 15 9 20 I 0867 16 9.00 1.0788 17 8.80 I 0704 18 860 I 0677 19 8 40 1.0733 20 8 20 1.0782 21 8 00 1.0814 22 7 80 I 0840 23 7 60 1.0844 24 7.40 1.0855 25 7 20 1.0857 26 7 00 1.0848 27 6 80 1.0816 28 6 60 I 0793 29 640 I 0776 30 6.20 1.0714 31 600 1.0674 32 5 80 1.0639 33 5 60 1.0613 34 5 40 1.0563 35 5 20 1.0675 36 5 00 I 0802 37 4.80 1.0939 38 4 60 I 1089 39 440 I 1226 40 4 20 I 1355 41 4 00 I 1473 42 3 80 I 1630 43 3.60 I 1811 44 3 40 I 1975 45 3 20 I 2131 46 3.00 1.2264 47 2 80 I 2477 48 2 60 1.2814 49 2 40 I 3173 50 2.20 1,3537 51 2 00 I 3913 52 1.80 14284 53 1.60 1.4640 54 140 14984 55 120 I 5310 56 I 00 I 5609 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 10 oflS

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 c

~

~

"0

.c -:i Q.

~

rJ:J -

c =

*;;; =
g.

..:.= c

~ =

"0 =

==

225 200 175 150 125

~

100 75 50 25 0

0.0

~

~,

(0, 114) 0.1 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive

.~

(.552, 225)

'/

~

II',

I~

'/,

Banke

./,

1,1 II' I"

1,1 II',

iJI

'/,

BankO

~

.I,

I~

II',

  • ~

'/

~

~ (.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 July 2017 (1, 187) -

.I,

I" iJI

~

0.9 1.0 Fully Withdrawn shall be the condition where control rods are at a position within the interval 2:: 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 OPERA TrNG LIMITS REPORT. FNP UNIT 2 CYCLE 26 July 2017 Figure 2 K(Z) -Normalized F Q(Z) as a Function of Core Height 1.2 I.

Q -

u co:

[;!;,

0.8

~

=

i!

co:

qj

g.

"CI qj 0.6 E

I.

Q z Core Height (ft.)

K(Z) 0.000 1.000 N -

6.000 1.000

t 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

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 26 July 2017 c:z::

~

~

0

=-

..J <

c:z::

~

c F-Q

~

F-

~

Q

R Col
1:

Q

=-

120 110 100 90 1--

80 70 60 50 40 30 20 10 0

-60 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC

(-12, 100)

(+9, 100)

I UNACCEPTABLE l

~

OPERATION J

\\

I v r ACCEPTABLE

~

OPERATION I

\\

1\\

I 1\\

I UNACCEPTABLE I

OPERATION

(-25, 50)

(+24, 50)

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 Axial Flux Difference (Delta I) %

Page 13 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 680 IO...

660 lo...

640 X....

600 580 560 0.0 r--...

r-....

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

I'-..

'I'-..

I I

0.2 Figure 4 Reactor Core Safety Limits UNACCEPTABLE I OPERATION I

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

......~'--

I'-..

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

r--...

1'-....

r-....

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

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

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

r--...

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

r-.....

r--.....

~""'-I'-..

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

r........

r----:-...

ACCEPTABLE I

I'-..

OPERATION I

0.4 0.6 0.8 1.0 Power (Fraction of RATED THERMAL POWER)

July 2017

""q_

\\

>--- 2425 psig

\\

--o-- 2235 psig

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

-..r-1985 psig

\\

-x-1825 psig

')

['..

~

1.2 Page 14 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

!!... s y c.

'-"... =

- 24. 0

~

. ~ -24. 5 y

E

~

Q u

~ =

... E

~

c. s

~ -25. 0 I.

Q... E

~

'C Q ::;

-25. 5 16000 r-..........

~

....... ~

r-.....

~~

17000 18000 19000 Cycle Burnup (MWD/MTU)

Cycle Burnup Moderator Temperature (MWD/MTU)

Coefficient (Ecm/°F) 16000

-24.37 17000

-24.62 18000

-24.84 19000

-25.08 20000

-25.31 July 2017

....... ~

20000 Page 15 of 15

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