NL-19-1384, Cycle 30 Core Operating Limits Report

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Cycle 30 Core Operating Limits Report
ML19323D818
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 11/19/2019
From: Gayheart C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-19-1384
Download: ML19323D818 (17)
v • d • e


Text

~ Southern Nuclear NOV 1 9 2019

(

Docket No.:

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 30 Core Operating Limits Report Ladies and Gentlemen:

3535 Colonnade Parkway Birmingllam, AL 35243 205 992 5000 tel 205 992 7795 fax NL-19-1384 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 1 Cycle 30 Version 1.

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

Respectfully submitted, C eryl yheart Regulatory Affairs Director CAG/was/scm

Enclosure:

Core Operating Limits Report for FNP Unit 1 Cycle 30 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 30 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 30 Version 1

SOUTHERN<<\\

COMPANY Energy to Serve Your World*

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 30 Version 1 June 2019

CORE OPERATING LIMITS REPORT. FNP UNlT I CYCLE 30 June 2019 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT I CYCLE 30 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 I and 2 (with ke1T ::::: I)

The Technical Specifications affected by this repmi are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN-MODES 2 (with kerr< I) 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,{,1 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 I of 15

CORE OPERATING LIMITS REPORT, FNP UNIT J CYCLE 30 June 2019 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section I.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 ken*:2: 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGrN shall be greater than or equal to 1.77 percent L'.k/k.

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

2.2.2 Mode 5-The SHUTDOWN MARGfN shall be greater than or equal to 1.0 percent L'.k/k.

Page 2 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 20 19 2.3 Moderator Temperature Coefficient (Specification 3. 1.3) 2.3. 1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLl ARO-MTC shall be less than or equal to +0.7 x I 0-4 ~k/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 ~klk/°F at 100 percent RTP.

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

2.3.2 The MTC Survei llance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-3.65 X ] 0-4 ~k/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 of 300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcmr F or (~AFD

  • AFD Sensitivity)}

where: ~AFD 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 pcmr F I ~AFD

      • Predictive Correction is -3 pcmr F.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 104 ~k/k/°F.

where: BOL stands for Beginnjng 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 LlMlTS REPORT, FNP UNIT I CYCLE 30 June 2019 2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insettion as shown in Figure l.

2.6 Heat Flux Hot Channel Factor-F0 (Z) (Specification 3.2.1)

FliT!'

2.6.1 F0 (Z) ~ __g______

  • K(Z) p for P > 0.5 for P::;; 0.5 where:

p =

THERMAL POWER RATED THERMAL POWER 2.6.2 F;m* =2.50 2.6.3 K(Z) is provided in Figure 2.

2.6.4 F 1171' *K(Z)

F (Z) < - 0=-

9 P*W(Z)

F 117*p

  • 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 I.

Page 4 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 2.7 Nuclear Enthalpy Rise Hot Channel Factor-F; (Specification 3.2.2) 2.7.1 F N < F 1111, * ( I + P F * (1 - P))

H-M l M l where:

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

RATED THERMAL POWER 2.7.2 F~J" = 1.70 2.7.3 PF,.,., = 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 I 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 Ove1temperature ~T COT~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 Ove1temperature ~ 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 k,rr ~ 0.95 (all rods in less the most reactive rod) and subcriticality (illl rods out) over the entire cycle. This concentration includes additional boron to address unce1tainties and B 10 depletion.

Page 5 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 Table 1 Fo(Z) Penalty Factor Cycle Burnup F Q(Z) Penalty (MWDfMTU)

Factor 0

1.0422 150 1.0422 354 1.0506 559 1.0560 763 1.058 I 968 1.0567 1172 1.0520 1377 1.0449 I 58 I 1.0367 1786 1.0283 I990 I.0205 2195 1.0200 7306 1.0200 7510 1.0248 7715 1.0261 7919 I.0274 8I24 1.0233 8328 1.0216 8532 1.0200 Notes:

1. The Penalty Factor, to be applied to F0(Z) in accordance with SR 3.2.1.2, is the maximum factor by which F0(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) star1ingfrom the burnup at which the F0(Z) was determined.
2.

Linear interpolation is adequate for intermediate cycle burnups.

3. For all cycle burn ups 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 I CYCLE 30 June2019 Table 2 Reactor Trip System Instrumentation-Overtemperature 11T (OT/1T)

Setpoint Parameter Values T' $ 577.2°F K1 = 1.17

'tl :::: 30 sec

'!4 = 0 sec h(/11) =

P' = 2235 psig

-r2 $ 4 sec

-rs ~ 6 sec

-2.48 {23 + (qt-qb)}

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

1<3 = 0.000825/psi when (qt-qb) $-23% RTP when -23% RTP < (qt -qb) ~ 15% RTP when (qt-qb) > 15% RTP Page 7 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 30 Axial Elevation Point (feet) 1 12.00 2

I 1.80 3

I 1.60 4

11.40 5

I 1.20 6

I 1.00 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 5.40 35 5.20 36 5.00 37 4.80 38

<1.60 39 4.40 40 4.20 41 4.00 42 3.80 43 3.60 41 3.40 45 3.20 46 3.00 47 2.80 48 2.60 49 2.40 50 2.20 5"1 2.00 52 1.80 53 1.60 5!

1.40 55 1.20 56 1.00 57 0.80 58 0.60 59 0.40 60 0.20 61 0.00 ISO MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 LI992 1.2003 1.1 955 1.1 933 Ll899 1.1 848 1.1 790 1.1 727 1.1 654 1.1588 1.1 539

1. 1460
1. 1432 1.1 524 1.1 606 1.1 673 1.1 721
1. 1746 Ll 758 1.1 748 Ll 73 1 1.1708 LI 668
1. 162 1 1.1 568 1.1505 1.1434 1.1 357 1.1286 LI 265 1.1 336
1. 1408 1.1 475
1. 1536 1.1587 1.1 63 1 1.1 664 1.1 707
1. 1765 1.1 8 18 1.1 85~

1.1 949 1.2 183 1.2446 1.2707 1.2969 1.3228 1.3475 1.37 11 1.3933 1.4 137 LOOOO 1.0000 1.0000 1.0000 1.0000 Table 4 RAOCW(Z) 3000 6000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1842 1.2322 1.1842 1.2303 LI 78 1 1.2228 1.1 754 1_2 190 Ll71 6 1.2178 1.1 661 1.2 111 LI600 1.2100

1. 1534 1.2070 1.1469 1_2018 1.1457 LI 948 1.1 599 1.1897 1.1687 1.1 972 1.1772 1.2039 1.1863 1.2 127 Ll940 1.2 190 LI 994 1.2230 1.2028 1.2249 1.2035
1. 224 1 1.2028 1.2220 1.199' 1.2 167 Ll 94 1 1.2105 Ll 877 1.2036 1.1 795 1.1 948 Ll 703 Ll 848 1.1603 1.1 738 1.1493 LI 6 19 Ll 376 1.1494 1.1252 1.1391 1.11 76 1.1 298 1.1 276 1.1 226
1. 1354 1.123 1 1.1 432 1.1 290 1.1 503 1.1339 1.1 568 1.1 384 1.1 623 1.142 1 1.1 67 1 1.1452 1.1 710 1.1471 1.1 740 1.1497 1.1 756 1.1 540 1.1 797 1.1572 1.188 1 1.1633 1.2123 1.1 751 1.2422 1.1883 1.27 13 1.2003 1.301 2 1.2 189 1.33 10 1.2385 1.3604 1.2576 1.3885 1.276 1 1.415 1 1.2938 1.4400 1.3 104 1.4626 1.3258 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.2369 1.2358 1.2294 1_2228 L2 16 1 1.2089 1.2014 1.1937
1. 1857 1.1 802 1.1 813 1.1 787 1.1 8 14 1.1 946 1.205 1 1.2134 1.2 194 1.2230 1.225 1 1.2237 1.2204 1_2 169 1.2 117 1.2050 1.1970 1.1878
1. 1777 1.1 666 1.1 584 1.1 590 1.1 598 1.1610 1.1 609 1.1 599 1.1 578
1. 1548 1.1 50 1 1.1440 I. 1373 1.1 306 1.1288 1.1373 1.1 5 11 1.1642 1.1 777 1.1 904 1.2026 1.2149 1.2270 1.2386 1.2497 1.0000 1.0000 1.0000 1.0000 1.0000 Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

June 20 19 14000 18000 MWD/MTll MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2118 1.2384 1.2 11 2 1_2304 1.2039 1.2121 LI97 1 LI976

1. 1905 1.1 904 I LI 856 LI837 1.1883 Ll 765 Ll 945 Ll7 14 1.20 15 LI703 1.2044 Ll 737 1.2 167 Ll 86 1 1.222 1 1.1924 1.2329 Ll955 1.25 13 1.2046 1.2659 1.2251 1.2775 1.2422 1.2865 1.2565 1.2925 1.2679 1.2966 1.2777 1.2961 1_2828 1.2930 1.2845 12891 1.2857 1.2830 1.285 1 1.2745 1.282 1 12637 1.2766 1.25 13 1.2696 1.2376 L26 11 1.2220 1.2509 1.2073 1.241 3 1.2070 1.2400 1.2045 1.2390 1.20 II 1.2363 1.1960 1.23 17 1.1 895 1.225 1 1.18 16 1.2 168 1.1 725 1.207 1 1.16 12 1.1 942 Ll 474 1.1 786 1.1 388 1.1 63 1 1.1 33 1 1.1 452 1.1 291 1.1468 1.1369 1.1 6 13 1.1 5 12 1.1 777 1.1647 1.1 949 l.l 785 1.2 120 1.1909 1.2274 1.2028 1.2420 1.2 150 1.2569 1.2272 1.27 19 1.2391 1.2868 1.2509 1.3016 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 9 of IS

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 Table 5 Part Power (48%) RAOC W(Z)

Axial Point E leva tion (feet)

ISO t'\\'IWD/MTll 1

12.00 1.0000 2

11.80 1.0000 3

I 1.60 1.0000 4

11.40 1.0000 5

11.20 1.0000 6

11.00 1.2722 7

10.80 1.2648 8

10.60 1.2525 9

10.40 1.2396 10 10.20 1.2 194 11 10.00 1.2072 12 9.80 L 1872 13 9.60 L 1598 14 9.40 1.1 389 15 9.20 L 11 94 16 9.00 1.102 1 17 8.80 1.0854 18 8.60 1.0750 19 8.40 1.076 1 20 8.20 1.0762 2 1 8.00 1.0792 22 7.80 1.0803 7.60 1.0794 24 7.40 1.080 1 25 7.20 1.0788 26 7.00 1.0775 27 6.80 1.0776 28 6.60 1.0759 29 6.40 1.0740 30 6.20 1.0724 3 1 6.00 1.0700 32 5.80 1.0667 33 5.60 1.0632 34 5.40 1.0622 35 5.20 1.066 1 36 5.00 1.0790 37 4.80 1.0914 38 4.60 1.1 033 39 4.40 1.11 48 40 4.20 1.1 254 41 4.00 1.1 347 42 3.80 1.1445 43 3.60 1.1 560 44 3.40 1.1697 45 3.20 1.1829 46 3.00 1.1 938 47 2.80 1.2 102 48 2.60 1.2385 49 2.40 1.1701 50 2.20 1.302.1 51 2.00 1.3369 52 1.80 1.37 13 53 1.60 1.4050 54 1.40 1.4.172 55 1.20 1.4672 56 1.00 1.4953 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20 1.0000 6 1 0.00 1.0000 Top and bottom 5 axial points excluded per Tcchnic.al Specification B3.2.l.

Page 10 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT l CYCLE 30 225 200 175

..-. =

~ 150 "0

.c -

~

~ 125

~

(f)

'-" =

.8

  • ~ 100 0 c..

..:.:: =

e.:

~ 75

~

50 25

~

0 0.0 1/

II' (0, 114)

~

0.1 Figure I Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive I

1/

(.552, 225) 1/

II""

~,

~

~

~

BankC 1/

II'

~

~

1/

~

il"'"

1/*

~ Bank D il"'"

1/

~

_/

~

r

~

~

~ (.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 June 2019 (1, 187) -

1/

v il"'"

~

~

0.9 1.0 Fully Withdrawn shall be the condition where control rods are at a position within the interval ::2:225 and

23 I steps withdrawn.

Note: The Rod Bank Lnsertion 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 II of 15

CORE OPERA TJNG LIMITS REPORT, FNP UNIT I CYCLE 30 June 2019 Figure 2 K(Z)- Normalized FQ(Z) as a Function of Core Height 1.2 0........

co; eo..

0.8 OJ) c

i!

co;

~

Cl..

"0 4.1

.!::l co; E

0.6 -

0 z Core Height (ft.)

K(Z)

N

~

0.000 1.000 6.000 1.000 12.000 1.000 0.4 FQ = 2.50 I

0.2 0

0 2

4 6

8 10 12 Core Height (feet)

Page 12 of 15

CORE OPERATING LIM ITS REPORT. FNP UNIT I CYCLE 30 120 110 100

,..., 90 1:1::

f--

~

~

0 80 Q.,

...:l

~

~ 70 1:1::

~ =

E-60 Q

~

E-

~ 50 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC

(-12, 100)

(+9, 100) v UNACCEPTABLE I

~

OPERATIO '

I

\\

/ v r ACCF:JYrABLE

~

OPERATIO I

v 1\\

June 2019 J

U 'ACCEJ>TABLE l

OPERATION 0

(-25, 50)

(+24, 50)

R "

~

~

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

CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 30 680 lo.....

660 -

lo....

640 x.....

600 580 560 0.0 I'-

1'--

r-.............,

I'-.......,

1'--

I I

0.2 Figure 4 Reactor Core Safety Limits NACCEPTABLE I OPERATIO I

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

I'-I'-

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

r-....

t-....

i"--.......,

~J

-..... 1'--

r-...... I'-!'--,

I'-

i'--

r-......

I'-

-..... 1'--

-..... 1'--

b-.,

i"--1'--

r-....

!"'---i'--

ACCEPTABLE I

OJ>ERATION I

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

June 2019 M

1'\\

-v-2425 psig

\\

-a-2235 psig

!"'---j--..,.-, \\

-..r-1985 psig 1\\

-x-1825 psig

\\

!"'---r-......

f'.....x 1.2 Page l4 of 15

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURN UP

- 23. 5 1-*

+l d

Q)

'8 - 24. 0 r--....

  • .-I 11-1 11-1 Q) 0 u Q) 1-1
l

+l I'd 1-1

~ - 24. 5 al E-<

1-1 0

+l I'd 1-1 Q)

'0

~

1-

- 25. 0 16000 r--....

~

,____ 1--

...... I '

17000 18000 19000 Cycle Burnup (MWD/MTU)

Cycle Burnup (MWD/MTU)

!6000

!7000

!8000 19000 20000 Moderator Temperature Coefficient (pcm/°F)

-23.95

-24.20

-24.43

-24.69

-24.9 1 June 2019 1'-o..

20000 Page 15 of 15

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