NL-14-1791, Cycle 24 Ore Operating Limits Report Version 1

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Cycle 24 Ore Operating Limits Report Version 1
ML14315A052
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 11/11/2014
From: Pierce C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-14-1791
Download: ML14315A052 (17)
v • d • e


Text

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

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN << \

November 11, 2014 COMPANY Docket Nos.: 50-364 NL-14-1791 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Unit 2 Cycle 24 Core Operating Limits Report Version 1 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 24 Version 1.

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

Sincerely, t fi fL..

C.R. Pierce Regulatory Affairs Director CRP/RMJ/Iac

Enclosure:

Core Operating Limits Report for FNP Unit 2 Cycle 24 Version 1

U. S. Nuclear Regulatory Commission NL-14-1791 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, 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 Mr. R. R. Martin, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, 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 24 Core Operating Limits Report Version 1 Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 24 Version 1

SOutHERN_.\

COMPANY Energy to Serve lOur World*

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 -Cycle 24 Version 1 September 2014

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 20 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 24 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 ken;;::.: 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< 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:u 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 13

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 24 SEPTEMBER2014 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 I and 2 (with ketr~ 1.0) (Technical Requirement 13.l.l) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to I. 77 percent llk/k.

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

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

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 ~klk/°F for power levels up to 70 percent R TP with a linear ramp to 0 ~k/k/°F at t 00 percent RTP.

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

The 100 ppm/ARO/RTP-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.

Page 2 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 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- F0 (Z) (Specification 3.2.1) for P >0.5 for P ~ 0.5 THERMAL POWER where: P=-------------------

RATEDTHERMAL POWER 2.6.2 Ft!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,.__ _ _ for P ~ 0.5 Q - O.S*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 l.

Page 3 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F~ (Specificati.on 3.2.2) 2.7.1 F~ ~F!'P*(I+PFM~*(I-P))

THERMAL POWER where: 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) 2.10.1 In MODES 1 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 (OT!lT) and Ovemower !lT COP!lTl 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 ~ 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 (ru! rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.

Page 4 of 13

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 24 SEPTEMBER 20 14 Table 1 FQ(Z) Penalty Factor Cycle Burnup F0 (Z) Penalty (MWD/MTU) Factor 5459 1.0200 5663 1.0214 5867 1.0236 6071 1.0260 6275 1.0264 6480 1.0250 6684 1.0232 6888 1.0210 7092 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 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) starting from the bumup at which the F0 (Z) was determined.
2. Linear interpolation is adequate for intermediate cycle bumups.
3. For all cycle bumups outside the range of the table, a penalty factor of 1.0200 shall be used.

Page 5 of 13

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Table 2 Reactor Trip System Instrumentation- Overtemperature aT (OTaT)

Setpoint Parameter Values P' = 2235 psig K, = 1.17 K.3 = 0.000825/psi t1;:::: 30 sec t4= 0 sec t6:S: 6 sec

-2.48 {23 + (qt- qb)} when (qt- qb) s -23% RTP 0% ofRTP when -23% RTP < (qt -qb) :S: 15% RTP 2.05 {(qt- qb) - 15} when (qt- qb) > 15% RTP Page 6 of 13

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Table 3 Reactor Trip System Instrumentation- Overpower ll.T (OPll.T)

Setpoint Parameter Values

~= 1.10 Ks = O.oz;oF for increasing Tavg K6 = 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 h(/11) = 0% RTP for all/11 Page 7 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Table 4 RAOCW(Z)

Axial Point Elevatioa (feet) 1SOMWD/MTU 3000 MWD/MTU 10000 MWDIMTU 14000 MWDIMTU 18000 MWDIMTU

  • 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 3

4 11.80 11.60 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 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 6 11.00 1.1235 1.1452 1.2675 1.2613 1.2533 7 10.80 l.l213 1.1446 1.2602 1.2522 1.2426 8 10.60 1.1162 1.1391 1.2390 1.2332 1.2206 9 10.40 1.1110 1.1330 1.2244 1.2146 1.1961 10 10.20 1.1051 l.l316 1.2219 1.1933 1.1846 11 10.00 1.1110 u2n 1.2198 l.l958 1.1779 12 9.80 1.1143 1.1290 1.2244 1.2012 1.1708 13 9.60 1.1167 1.1286 1.2251 1.2085 1.1631 14 9.40 1.1155 1.1264 1.2275 1.2097 1.1611 15 9.20 l.ll86 l.l231 1.2253 1.2226 1.1712 16 9.00 1.1183 1.1188 1.2342 1.2314 1.1981 17 8.80 1.1208 1.1121 1.2365 1.2357 1.2280 18 8.60 1.1374 1.1085 1.2403 1.2372 1.2543 19 8.40 1.1502 1.1167 1.2535 1.2464 1.2779 20 8.20 1.1611 1.1267 1.2642 1.2622 1.2979 21 8.00 l.l702 1.1349 1.2726 1.2747 1.3151 22 7.80 l.I767 1.1410 1.2772 1.2834 1.3277 23 7.60 1.1810 l.l454 1.2791 1.2895 1.3370 24 7.40 l.l838 l.l487 1.2790 1.2937 1.3441 25 7.20 1.1843 l.l501 1.2750 1.2935 1.3460 26 7.00 1.1832 1.1510 1.2682 1.2909 1.3437

'Zl 6.80 1.1805 1.1508 1.2594 1.2870 1.3389 28 6.60 l.l766 1.1497 1.2491 1.2814 1.3320 29 6.40 1.1713 1.1474 1.2366 1.2732 1.3221 30 6.20 1.1649 1.1440 1.2223 1.2628 1.3094 31 6.00 1.1575 1.1399 1.2067 1.2506 1.2947 32 5.80 1.1495 1.1352 l.l904 1.2374 1.2789 33 5.60 1.1416 1.1308 1.1753 1.2223 1.2607 34 5.40 1.1443 1.1411 1.1689 1.2088 1.2412 35 5.20 l.l576 1.1519 1.1682 1.2082 1.2378 36 5.00 1.1693 1.1622 1.1680 1.2064 1.2339 37 4.80 1.1807 1.1719 l.l668 1.2036 1.2306 38 4.60 1.1915 1.1811 1.1645 l.l991 1.2251 39 4.40 1.2016 1.1895 l.l611 1.1932 1.2177 40 4.20 1.2105 1.1969 1.1569 1.1860 1.2088 41 4.00 1.2184 1.2034 1.1519 l.l776 1.1984 42 3.80 1.2256 1.2097 1.1453 u6n 1.1849 43 3.60 1.2316 1.2170 1.1370 1.1539 1.1687 44 3.40 1.2383 1.2240 1.1300 1.1450 1.1523 45 3.20 1.2455 1.2301 1.1245 1.1387 1.1344 46 3.00 1.2607 1.2339 1.1219 1.1370 1.1390 47 2.80 1.2833 1.2470 1.1276 1.1463 1.1556 48 2.60 1.3061 1.2651 1.1376 l.l606 1.1709 49 2.40 1.3283 1.2868 1.1473 1.1743 1.1868 50 2.20 1.3499 1.3134 1.1574 l.l882 1.2027 51 2.00 1.3771 1.3401 1.1667 1.2008 1.2170 52 1.80 1.4053 1.3662 1.1758 1.2128 1.2306 53 1.60 1.4316 1.3909 l.l8S1 1.2250 1.2446 54 1.40 1.4563 1.4140 1.1945 1.2373 1.2591 55 1.20 1.4791 1.4354 1.2038 1.2494 1.2735

.* 56

'S7 1.00 0.80 1.4995 1.0000 1.4546 1.0000 1.2129 1.0000 1.2613 1.0000 1.2879 1.0000

.* 58 59 60 0.60 0.40 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000

Page 8 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Table 5 Part Power (48o/o) RAOC W(Z)

Axial Point Elevation (feet) lSOMWD/MTU

..

  • 1 2

3 12.00 11.80 11.60 1.0000 1.0000 1.0000

  • 4 11.40 1.0000
  • 5 11.20 1.0000 6 11.00 1.2173 7 10.80 1.2038 8 10.60 1.1857 9 10.40 1.1663 10 10.~0 1.1453 11 10.00 1.1357 12 9.80 1.1~32 13 9.60 1.1086 14 9.40 1.0916 15 9.20 1.0817 16 9.00 1.0694 17 8.80 1.0620 18 8.60 1.0701 19 8.40 1.0762 20 8.20 1.0818 21 8.00 1.0865 22 7.80 1.0900 23 7.60 1.0924 24 7.40 1.0943 25 7.20 1.0949 26 7.00 1.0946 27 6.80 1 09~6 28 6.60 1.0862 29 6.40 1.0813 30 6.20 1.0783 31 6.00 1.0740 32 5.80 106'19 33 5.60 1.0673 34 5.40 1.0754 35 5.20 1.0936 36 5.00 1.1104 37 480 1.1271 38 4.60 1.1432 39 4.40 1.1587 40 4.20 1.1728 41 4.00 1 1860 42 3.80 12001 43 3.60 12131 44 3.40 1.2269 45 3.20 12410 46 3.<Kl 1.2630 47 2.80 1.2925 48 2.60 1.3224 49 2.40 1.3508 50 ~.20 1.3790 51 ~-00 1.4152 52 1.80 1.4522 53 1.60 1.4869 5-l 1.40 1.5202 55 1.20 1.5515 56 1.00 1.5805 57 0.80 1.0000 58 ()60 1.0000

. . 59 60 61 0.40 0.20 0.00 1.0000 10000 1.0000

  • Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

Page 9 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225

~ . (.552, 225)

~

200

~

~ (1, 187)

I"

~

175 It' ~

~

j 150 ~

I.J BankC

.,1! ~ I"

~

~

Ill , ~ I.'

~

-Q.

Gl

!e c

0 125

~

(0, 114) ~

~

E Ill 0

a.

100 ...,

~ ~ BankO c I" CD l.fj

& 75 I.'

50

~

25 I" 1.1 I.' (.070, 0) 0 I J LJ I 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 10 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 20 I4 Figure 2 K(Z)- Normalized FQ(Z) as a Function of Core Height 1.2 I

1 I I

0 u

ftS 0.8 Ii LL.

C) c I

i2 ftS i CD I D.

.~ 0.6 ii e

0 ---- --

Core Height (ft.)

0.000 K(Z) 1.000 z 6.000 1.000 N

~ 0.4 12.000 1.000 I

FQ=2.50 0.2 c----r--- I

_l 0

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

Page II of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110 1 (*12, 100) (+9, 100) 100 90

!-- UNACCEPTABLE .

  • .. ~P... ~-~ tQr . . .

v ~

UNACCEPTABLE

~ ~*-~

-~ F'.ERAT ON . .

1--

~

Ill

~D. 80 J \

v

~

-~---

ACCEPTABLE

~ O.F'ERATION

E 70 a:

I

'1\

Ill

c Q 60 l.

Ill i0 50 I

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

!.... 40 I

D.

30 20 10 0

-60 -50 -40 *30 -20 *10 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %

Page 12 oft3

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 SEPTEMBER 2014 Figure 4 Reactor Core Safety Limits 680 I

J UNACCEPTABLE I~

I OPERATION 680 I'-- r-...

!"'-- .......... I t---..

.c... 1'-- ..........

!'-. I'- i

.......... .......... ~

840

......... r---. 1'-- ...... I .........

~

.......... ~

......... I'-- ~ i\ ~2425psig lx.... ......... '""r--... b-.  !"'-- ......... \ -o-2235 psig I'-- .........

I'-- r-.,., \ --6-1985 psig

-x-1825 pslg

......... I 1'-- ......... \

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

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

600 r..... .........

1'-- ;..........

I ACCEPTABLE OPERATION I ~

.... ~

I J 680 I

I 660 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)

Page 13 of 13

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