NL-15-0909, J. M. Farley, Unit 1 - Cycle 27, Version 1, Core Operating Limits Report

J. M. Farley, Unit 1 - Cycle 27, Version 1, Core Operating Limits Report

ML15138A370
Person / Time
Site:	Farley
Issue date:	05/18/2015
From:	Pierce C Southern Company Services, Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-0909
Download: ML15138A370 (16)

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 SOUIHI COMPANY May 18,2015 Docket Nos.: 50-348 NL-15-0909 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 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 1 Cycle 27 Version 1.

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

c.te-Sincerely, C.R. Pierce Regulatory Affairs Director CRP/RMJ

Enclosure:

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

U.S. Nuclear Regulatory Commission NL-15-0909 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. A. 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 Requlatorv 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 1 Cycle 27 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 27 Version 1

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 FEBRUARY 2015 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT l 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 l and2 (with kerr;::: 1)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits f<;>r 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 Instrwnentation Overtemperature AT (OTAT) and Overpower AT 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 13

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 FEBRUARY 2015 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 ken:> 1.0) (Technical Requirement 13 .1.1) 2.1.1 The SffiJTDOWN MARGIN shall be greater than or equal to 1.77 percent Aklk.

2.2 SHUTDOWN MARGIN- MODES 2 (with kdl'< 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 I.77 percent Aklk.

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

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3 .1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL/ARO-MTC shall be less than or equal to +0.7 x 104 Ak/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k/°F at I00 percent RTP.

The EOUARO/RTP-MTC shall be less negative than -4.3 x 104 Ak/k/°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 IO"' Ak/k/°F.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x IO"' Aklk/°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 of13

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 27 FEBRUARY 2015 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)

F.RTP 2.6.1 FQ(Z)s-Q-*K(Z) for P > 0.5 p

for P s 0.5 THERMAL POWER where: P=------------------

RA TED THERMAL POWER 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) s _Q!:...---- for P > 0.5 Q P*W(Z)

F.RTP

• K(Z)

F. (Z) s _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 ofl3

CORE OPERATING LIMITS REPORT. FNP UNIT l CYCLE 27 FEBRUARY 2015 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F~ (Specification 3.2.2) 2.7.1 F~ ~ F=P *(I + PFAH *(1-P))

THERMAL POWER where: P=-------------------

RA TED THERMAL POWER 2.7.2 2.7.3 PFAH =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.'

2.1 0 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1 .1) 2.1 0.1 In MODES l 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 Ovemower ~T (OP~T)

Semoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1)

2. I 1. 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. I2 RCS DNB Parameters for Pressurizer Pressure. RCS Average Temperature. and RCS Total Flow Rate (Specification 3.4. I)

2. 12. 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 temperatures 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 ofkerrS 0.95 (all rods in less the most reactive rod) and subcriticality (.!ill rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.

Page 4 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 27 FEBRUARY 2015 Tablel FQ(Z) Penalty Factor Cycle Burn up F 0 (Z) Penalty (MWD/MTU) Factor 30 1.0370 150 1.0370 354 1.0338 559 1.0302 763 1.0264 967 1.0238 1172 1.0222 1376 1.0201 1580 1.0200 4237 1.0200 4441 1.0204 4645 1.0244 4850 1.0245 5463 1.0248 5667 1.0246 6076 1.0338 6280 1.0304 6485 1.0265 6689 1.0208 6893 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 3 I 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 burn ups 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 1 CYCLE 27 FEBRUARY 2015 Table 2 Reactor Trip System Instrumentation- Overtemperature aT (OTaT)

Setpoint Parameter Values P' = 2235 psig K1 = 1.17 1<3 = 0.000825/psi t1 ~ 30 sec t2S: 4 sec t4= 0 sec tsS: 6 sec t6S: 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 1 CYCLE 27 FEBRUARY 2015 Table 3 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;oF when T > T" Ks = 0 ;oF for decreasing Tavg 1<6 = o;oF when T s T" t3~ 10 sec t4= 0 sec tsS 6 sec t6S 6 sec f2(AI) = 0% RTP for all AI Page 7 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 27 FEBRUARY 2015 Table 4 RAOCW(Z)

.* Axial Point 1

2 Elevation (feet) 12.00 11.80 t50MWDIMTU I 0000 1.0000 3000 1\fWD/MTU 1.0000 1.0000 10000 MWDIMTU 1.0000 1.0000 14000 MWD/MTU 1.0000 1.0000 18000 MWD/MTU 10000 1.0000 3 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 4 11.40 I 0000 1.0000 1.0000 1.0000 1.0000 5 11.20 1.0000 I 0000 I 0000 1.0000 1.0000 6 11.00 1.113S 1.1146 1.2697 1.2319 1.2220 7 10.80 1.1112 1.1168 1.2666 1.2294 1.2196 8 10.60 I 1076 1.1134 1.2611 1.2246 1.2149 9 10.40 1.1060 1.1185 1.2546 1.2188 1.2094 10 10.20 1.1060 1.1291 1.2476 1.2160 1.2042 11 10.00 1.1141 1.1334 1.2396 1.2149 1.1992 12 9.80 1.1167 1.1316 1.2314 1.2131 1.1941 13 9.60 1.1206 11297 1.2251 1.2102 1.1884 14 9.40 1.1173 1.1220 1.2270 1.2063 1.1989 15 9.20 1.1203 1.1225 1.2343 1.::!032 1.2104 16 9.00 1.1::!30 11::!::!3 1.2390 1.2109 1.:!29S 17 8.80 11319 1.1 255 1.2382 1.2153 1.2419 18 8.60 1.1414 1.1356 1.2403 1.2193 1.2S08 19 8.40 1.1526 1.14S2 1.2505 1.2301 1.26111 20 11.20 1.16.."9 1.1543 1.2583 1.2441 1.2811

!1 8.00 1 1715 1.1611 12633 1.2548 1.2978 22 7.80 1.1781 1.1672 1.2660 1.2629 1.3112 23 7.60 1.1817 1.1701 1.2656 1.2679 1.3209 24 7.40 1.1840 1.1717 1.2636 1.2714 1.3286 25 7.20 1.1841 1.1711 1.2578 1.2707 1.3311 26 7.00 1.1827 1.1689 1.2SO.S 1.2674 1.3298 27 6.80 1.1797 1.1655 12424 1.2637 1.3264 28 6.60 1.1748 1.1603 1.2322 1.2579 1.3202 29 6.40 1.16!12 1.1543 1.220S 1.2502 1.311S 30 6.20 1.1630 1.1478 I 2074 1.::!407 1.3003 31 6.00 1.1555 1.1401 1.1931 ).2;,}7 1.2871 32 '-80 1.1471 11317 1.1806 1.2175 1.2726 31 S60 1.1380 1.1265 11712 1.2064 1.25S7

w S.40 1.13::!7 1. 1393 1.1 S9S 1.2031 1.2360 35 S.20 1.1433 I 1514 1.1540 1.2002 1.2337 36 5.00 1.1511 1.1631 1.1 S35 1.1958 1.2298 37 4.80 1.1612 1.1742 1.1525 1.1908 1.2245 38 4.60 1.1713 1.1847 1.1506 1.1864 1.2173 39 4.40 1.1808 1.1947 1.1478 1.1809 1.2083 40 4.20 1.1891 1.2035 1.1441 1.1741 1.1979 41 4.00 1.1'173 1.2115 1.1397 1.1664 1.1860 42 3.80 1.2082 1.2187 1.1337 1.1563 1.1714 43 J.liO 1.2201 1.2250 1.1300 1.14S3 I.IS39 44 3.40 1.2304 1.2302 1.1281 1.1379 1.139S 4S 3.20 1.2393 1.2347 1.1250 1.1308 1.1283 46 3.00 12475 1.2478 1.1219 1.1184 1.1241 47 2.80 1.2549 1..2774 1.1175 1.1286 1.1304 411 2.60 1.2790 1.3109 1.1215 1.1296 1.1416 49 2.40 1.3079 1.3433 1.1320 1.1307 I. IS33 50 2.20 13359 1.l764 1.1429 1.1405 1.167J 5I 2.00 13639 1.4000 I.IS30 1.1507 1.1799 52 1.80 1.3913 14411 1.1629 1.1602 1.1919 53 1.60 1.4170 1.4711 1.1728 1.1701 1.2043 54 1.40 1.4411 1.4992 1.1827 1.1803 1.:!170 55 1.20 1.4634 I.S2SO 1.111"..3 1.1904 1.2:!97 56 100 1483S 1.5481 1 201S 12004 1.24:!5 57 0.80 I 0000 1.0000 1.0000 1.0000 1.0000

• 58 0.60 I 0000 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 I 0000 1.0000 60 020 I 0000 1.0000 1.0000 I 0000 I 0000 61 0.00 1.0000 1 0000 1.0000 1.0000 t.oono

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

Page 8 of13

CORE OPERATING LIMITS REPORT. FNP UNIT l CYCLE 27 FEBRUARY 2015 Table 5 Part Power (48%) RAOC W(Z)

Axial Point Elevation (reet) 150MWD/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 l.lti07 7 10.80 11520 8 10.60 1.1427 9 10.40 1.1361 10 10.20 1.1309 11 10.00 1.1252 12 9,80 1. 1134 13 9.60 1.1083 14 9.40 1.0933 15 9.20 1.0905 16 9,00 1.0662 17 8,80 1.0663 18 8,60 1.0697 19 8.40 1.0752 20 8.20 1.0757 21 8.00 1.()792 22 7,80 1.0822 23 7.60 1.0827 24 7,40 1.0840 25 7.20 1.0847 26 7.00 1.0842 27 6.80 1.0805 211 6.60 1.0787 29 6.40 1.0778 30 6.20 I 0713 31 6.00 1.0675 32 5,80 1.0636 33 5.60 1.!1604 34 5.40 1.0607 35 5.20 1.0760 36 5.00 1.08Q7 37 4.80 1.1047 38 4.60 1.1207 39 uo l 1356 40 4.20 1.1493 41 4.00 1.1635 42 3.80 1.1811 43 3.60 1.1997 44 3.40 1.2174 45 3.20 1.23*10 46 3.00 1.2498 47 2RO 1264K 48 2.60 1.2958 49 2.40 1.3321 50 2.20 1.3677 51 2.00 1.4039 52 1.80 1.4397 53 1.60 1.4746 54 1.40 1.5098 55 1.20 I 5423 56 1.00 I 5720 57 0.80 1.0000 58 060 1.0000 59 0,40 1.0000 60 0,20 1.0000 61 o.on l 0000

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

Page 9 of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 FEBRUARY 2015 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn- 225 to 231 steps, inclusive 226 - I I I I r-r-. (.552, 226) -

~~

r-200 I'

II (11 187) =

175

- .., ~~r-

- ~ i"'

1- - -

BankC c i"' ""'

r-

1:

~

150 I! I' - r-

'tl

.J:.

~

Ill

~ ~ r-ll. 125 ~

Ill

- r-

~

c 0 - (0, 114) I"

~ -

~ 1-Ill 0 100 -

Q. ~

J#. II . Bank D c .. I"

~

m - ,..,

'tl 75 1-

• t-

& I'

~

50 ~

I' -

I'

~ -

2& -

1-r- 7 ~ (.070, 0) -

. I I I I I 1-0 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 lO of 13

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 FEBRUARY 2015 Figure2 I

K(Z) -Normalized F Q(Z) as a Function of Core Height

~ 1.2 I

I I

I 1

s(,)

if 0.8 Q

c al G)

I

-- ---~ ---- ---

D.

I I

~

'i 0.6 e Core Height {ft.)

0.000 K{Z) 0 1.000 ---

z 6.000 1.000 I

12.000 1.000 N

~ 0.4 I

FQ= 2.50 0.2 0 i 0 2 4 6 8 10 12 Core Height (feet)

Page 11 ofl3

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 FEBRUARY 2015 Figure 3 Axial Flux Dift'ereoce Limits as a Fuoctioo of Rated Thermal Power for RAOC I

120 110 I1-12, 1001 (+9,100) 100 90 r--

UNACCEPTABLE I \ UNACCEPTABLE

~

QPEMT,QN_

J \ CPE&ATPN I

80

~....

< 10 ACCEPTABLE

~

'\

~ OPERATION I

a:

""j!:

I Q 60 5

'0 50

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

~

... 40

~

1:1.

30 20 10 0

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

Page 12 of13

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 FEBRUARY 2015 Figure 4 Reactor Core Safety Limits 680 T

0... -- I I UNACCEPTABLE OPERATION r-.... ..... I 660

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

r...... '  !

0., r..... .......

- * -- t::- ~ ~

- ~

........ lo.... t.....

640 1 -

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

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

r-.... r--... r-.... ..... r.....'""Q

~

! -- .... ........- - * - r-.... ..... ~ --->-- 2426 pslg X:: ........ ....... \

! ........ r-.... .....

\

~2236pslg 620 ...... ...... --

1:11 ....... ........ ........ ....... ........ -.r-1986 pslg

! r...... ...... -  !-...,.,

"--.....; .......; -X-1826 pslg

....... ....... - \

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

600 - ~

-- f-~

- r-.... --

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

~ - **-- -*l -

ACCEPTABLE l OPERATION - .....

~

&80 --- -* -- *~ -- 1--

-- *- 1---

- i-- - *r-- - -- ,_

&60 I 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)

Page 13 oft3