nrc: home page - joseph m. farley, units 1 & 2, …2015/11/02 · fnp unit 1 cycle 27 july2015...

Charles R. Pierce Regulatory Affairs Director

November 2, 2015

Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242

Tel 205.992.7872 Fax 205.992.7601

Docket Nos.: 50-348 50-424 50-364 50-425

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001

SOUTHERN•\ NUCLEAR

A SOUTHERN COMPANY

NL-15-2014

Joseph M. Farley Nuclear Plant (Farley), Units 1 & 2 Vogtle Electric Generating Plant (Vogtle), Units 1 & 2

Farley Unit 1 Cycle 27 Core Operating Limits Report Version 2 Farley Unit 2 Cycle 24 Core Operating Limits Report Version 2 Vogtle Unit 1 Cycle 20 Core Operating Limits Report Version 1 Vogtle Unit 2 Cycle 18 Core Operating Limits Report Version 2

Ladies and Gentlemen:

In accordance with Technical Specification (TS) 5.6.5.d for Joseph M. Farley Nuclear Plant (Farley) and Vogtle Electric Generating Plant (Vogtle), Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Reports (COLAs):

• Farley Unit 1 Cycle 27 Core Operating Limits Report Version 2 • Farley Unit 2 Cycle 24 Core Operating Limits Report Version 2 • Vogtle Unit 1 Cycle 20 Core Operating Limits Report Version 1 • Vogtle Unit 2 Cycle 18 Core Operating Limits Report Version 2

The enclosed Version 2 COLAs were revised to include an algorithm and figure for calculating the revised predicted near End of Life (EOL) moderator temperature coefficient (MTC). The enclosed Vogtle Unit 1 Cycle 20 COLR Version 1 also includes this algorithm and figure.

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

Rt~~p;:d, C. R. Pierce Regulatory Affairs Director

CRP/RMJ

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U.S. Nuclear Regulatory Commission NL-15-2014 Page2

Enclosures: 1. Farley Unit 1 Cycle 27 Core Operating Limits Report Version 2 2. Farley Unit 2 Cycle 24 Core Operating Limits Report Version 2 3. Vogtle Unit 1 Cycle 20 Core Operating Limits Report Version 1 4. Vogtle Unit 2 Cycle 18 Core Operating Limits Report Version 2

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. D. R. Madison, Vice President- Fleet Operations Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. M.D. Meier, Vice President- Regulatory Affairs Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley Mr. G. W. Gunn, Regulatory Affairs Manager- Vogtle 1 & 2 RType: Farley=CFA04.054; Vogtle=CVC7000

U.S. Nuclear Regulatory Commission Mr. L. D. Wert, Regional Administrator (Acting) Mr. S. A. Williams, NRR Project Manager- Farley Mr. L. M. Cain, Senior Resident Inspector- Vogtle 1 & 2 Mr. P. K. Niebaum, Senior Resident Inspector- Farley Mr. R. E. Martin, NRR Project Manager- Vogtle 1 & 2

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Farley Unit 1 Cycle 27 Core Operating Limits Report Version 2 Farley Unit 2 Cycle 24 Core Operating Limits Report Version 2 Vogtle Unit 1 Cycle 20 Core Operating Limits Report Version 1 Voqtle Unit 2 Cycle 1 B Core Operating Limits Report Version 2

Enclosure 1

Farley Unit 1 Cycle 27 Core Operating Limits Report Version 2

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CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 JULY2015

1 .0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report (COLR) for FNP UNIT 1 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 1 and 2 (with kerr~ 1)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for TIIERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with kerr< 1 ), 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 3. I .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

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CORE OPERATING LIMITS REPORT. FNP UNIT 1 CXCLE 27 JULY2015

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 and2 <with~> 1.0) {Technical Requirement 13.1.1)

2.1.1 The SHUIDOWN MARGIN shaH be greater than or equal to 1. 77 percent L\klk.

2.2 SHUTDOWN MARGIN - MODES 2 (with kerr< 1.0). 3. 4 and 5 (Specification 3.1.1)

2.2.1 Modes 2 Ckcrr < 1.0), 3 and 4 -The SHUTDOWN MARGIN shall be greater than or equal to 1. 77 percent L\klk.

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

Page 2 of 15

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2.3 Moderator Temperature Coefficient (Specification 3.1.3)

2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLIARO-MTC shall be Jess than or equal to +0.7 x 10-4 .l\klk/°F for power levels up to 70 percent RTP with a linear ramp to 0 .l\klk/°F at 100 percent RTP.

The EOLIAROIRTP-MTC shaH be less negative than -4.3 x 10-4 AkfkiOF.

2.3.2 The MTC Surveillance limits are:

The 300 ppm/ AROIRTP-MTC should be Jess negative than or equal to -3.65 x 10-4 .l\klk/°F.

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

Revised Predicted MTC = Predicted MTC* + AFD Correction** + Pre~ictive

Correction***

where, * Predicted MTC is calculated from Figure 5 at the bumup corresponding to the measurement of300 ppm at RTP conditions, ** AFD Correction is the more negative value of:

{0 pcmrF or (AAFD * AFD Sensitivity)} where: AAFD is the measured AFD minus the predicted AFD fr

1om an

incore flux map taken at or near the bumup correspon4ing to 300ppm, AFD Sensitivity = 0.07 pcmrF I AAFD

***Predictive Correction is -3 pcmJOF.

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

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

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CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 27 JULY2015

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 l.

2.6 Heat Flux Hot Channel Factor - Fg ( Z) (Specification 3 .2.1)

FRTP 2.6.1 FQ(Z)~-Q-•K(Z) p

F.RTP FQ(Z)~-Q-•K(Z)

0.5

forP> 0.5

for P ~ 0.5

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

2.62 FQRTP = 2.50

2.6.3 K(Z) is provided in Figure 2.

2.6.4 F.RTP. K(Z)

F. (Z) < _C!~--Q - P•W(Z)

F.RTP. K(Z) F. (Z) < _Q~--

Q - 0.5•W(Z)

forP>0.5

forP ~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


2. 7 Nuclear Enthalpy Rise Hot Channel Factor- F~ (Specification 3.2.2)

2.7.1 Fi:t 5-F:JP •(l+PFw •(1-P))

where: p = THERMAL POWER RATED THERMAL POWER

2.72 F:JP = 1.70

2.7.3 PF!JI =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 Figur~ 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 Overtemoerature 1:1 I COT 1:1 Tl and Overpower 1:1 I COPAT) Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) ·

2.11.1 The Reactor Trip System Instrumentation Overtemperature 1:1 I (OT 1:1 T) and Overpower liT (OP/:iT) setpoint parameter values for IS Table 3.3.1-1 are listed in COLR Tables 2 and3.

2.12 RCS DNB Parameters for Pressurizer Pressure. RCS Average Temperature. and RCS TotaLFlow 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 s: 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 bo\D\ds 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 \D\Certainties and B 10 depletion.

Page 5 of 15

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Table 1

F Q(Z) Penalty Factor

Cycle Burnup F o(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 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 FQ(Z) was detennined.

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

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Table2

Reador Trip System Instrumentation- Overtemperature AT (OTAT) Setpoint Parameter Values

K1= 1.17

t1 ~ 30 sec t4=0sec

n(M) =

P' = 2235 psig

l<3 = 0.000825/psi

t2~4sec

-rs~6sec T6~ 6 sec

when (qt- qb) ~ -23% RTP -2.48 {23 + (qt- qb)} 0% ofRTP 2.05 {(qt- qb) -15}

when -23% RTP < (qt -qb) ~ 15% RTP when (qt- qb) > 15% RTP

Page 7 ofl5

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CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 27 JULY2015

Table 3

Reactor Trip System Instrumentation- Overpower AT (OPAT) Setpoiot Parameter Values

T" ~ 577.2°F

1<4= 1.10

t3~ 10 sec t4=0 sec ts~ 6 sec 't6~6sec

Ks = 0.02;oF for increasing Tavg Ks = o;oF for decreasing Tavg

fa( AI) = 0% RTP for all.M

1<6 = 0.00109 ;oF when T > T" 1<6 = O;oF when T ~ T''

Page 8 of 15

• • • • •

• • • • •

CORE QPERAIJNG LIMITS REPORT. FNP UNIT 1 CYCLE 27

AdalPolnt 1 2 3 • 5 6 7 8 9

10 11 12 13 14 lS 16 17 18 19 20 21 22 23 24 25 26 71 28 29 30 31 32 33 34 35 36 :rJ 38 99 40 41. G 43 .. e 46 .., 48 49 50 51 52 53 54. 55 56 57 58 59 60 61

*

Elnadon (feet) 150 MWDIMl1J 12.00 1.0000 tUM> 1.0000 11.60 1.0000 11 .40 1.0000 11.20 1.0000 11.00 1.1135 IO.IKI 1.1112 10.60 1.1076 10.40 1.1060 10.20 1.1060 10.00 1.1141 9.1Kl 1.1167 9.60 1.1206 9.40 1.1173 9.20 1.1203 9.00 1.1230 8.80 1.1319 8.60 1.1414 , 8.40 1.1.526 8.20 1.16'29 8.00 1.1715 7.80 1.1781 7.60 1.1817 7.40 1.1840 7.20 1.1841 7.00 1.1827 6.80 1.1797 6.60 1.1748 6.40 1.1692 6.20 1.1630 6.00 1.1555 5.80 1.1471 5.60 1.1380 5.40 1.1327 5.20 1.1433 5.00 t.l517 4.80 1.1612 4.60 1.1713 4.40 t.l808 4.20 1.1891 4.00 1.1973 3.80 1.2012 3.60 1.2201 3.40 1.2304 3.20 1.2393 3.00 1.2475 2.80 1.2549 2.60 1.2790 2.40 1.3079 2.20 1.3359 2.00 13639 1.80 1.3913 1.60 1.4170 1.40 1.4411 1.20 1.4634 1.00 1.4835 0.80 1.0000 0.60 1.0000 0.40 1.0000 0.20 1.0000 0.00 1.0000

Table 4 RAOCW(Z)

3000 MWDIMTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.1146 1.1168 1.1134 1.1185 J.1291 J.J334 1.1316 1.1297 1.1220 1.1225 1.1223 1.1255 1.1356 1.1452 J.1543 J.l617 1.1672 1.1701 J.J717 1.1711 1.1689 1.16.15 1.1603 1.1543 1.1478 1.1401 1.l317 1.126.1 1.1393 J.l514 1.1631 1.1742 t.l847 1.1947 1.2035 1.2115 1.2187 1.2250 1.2302 1.2347 1.2478 1.2774 1.3109 13433 1.3164 1.4090 1.4411 1.4711 1.4992 1.5250 1.5481 1.0000 1.0000 1.0000 1.0000 1.0000

10000 MWDIMI'U 1.0000 1.0000 1.0000 1.0000 1.0000 1.2697 1.2666 1.261l 1.2546 1.2476 1.2396 1.2314 1.2251 1.2270 1.2343 1.23!l0 1.2382 1.2403 1.2505 1.2583 1.2633 1.2660 1.2656 1.2616 1.2571 1.2505 1.2424 1.2322 1.2205 1.2074 1.1931 1.1806 1.1712 l.l59S l.J540 1.1535 1.1525 1.1506 1.1478 1.1441 1.1397 t.l337 1.1300 t.l281 1.1250 1.1219 1.1175 l.l215 1.1320 1.1429 1.1530 1.16'29 1.1728 1.1827 t.l923 1.2015 1.0000 1.0000 1.0000 1.0000 1.0000

Top aod bottom !I uial points aduded per Tecbaieal Spedfieatioo 83.2.1.

~ .' ' . ,. ... ~

JULY2015

14000 MWDIMTU 18000 MWDIMI1J 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 1.0000 1.0000 1.0000 1.2319 1.2:Z20 1..2294 1.2196 1.22A6 1.2149 1.2188 1.20!U 1.2160 1.2042 1.2149 1.1992 1.2131 1.1941 1.2102 1.1884 1.2061 1.1989 1.2102 1.2104 1.2109 1.2295 1.2153 1.2419 1.2193 1.2508 1.2301 1.2618 1.2441 1.28ll 125411 12978 1.26'29 1.3112 1.2679 l.l201J 1.2714 1.3286 1.2707 1.331J 1.2674 1.3298 1.2637 1.3264 1.2579 1.3202 1.2502 1.lll5 1.2407 1.3003 1.2297 1.2871 1.2175 1.2726 1.2064 1.2557 1.2031 1.2360 1.2002 1.2337 t.t9S8 1.2298 1.1908 1.22.45 1.1864 1.2173 t.l809 1.20113 I.I741 1.1979 1.1664 1.1860 U563 1.1714 1.1453 1.1539 1.1379 1.1395 1.1308 1.1283 1.1284 l.l2A1 1.1286 1.1304 1.1296 t.l416 1.1307 t.l533 1.1405 1.1673 1.1507 1.1799 1.1602 1.1919 1.1701 1.200 1.1803 1.2170 1.1904 1.2297 1.2004 1.2425 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

Page9of15

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CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 27

Table 5 Part Power (48%) RAOC W(Z)

Axial Poiat Elevation (feet) 150MWDIMTU • 1 1~.00 1.0000 • 2 11.80 1.0000 • 3 11.60 1.0000 • .& 11.-W I 0000 • 5 11~0 1.0000

6 11.00 1.1607 7 10.80 1.1.5:!0 8 10.60 1.1427 9 10.40 1.1361

10 10~0 1.1309 11 10.00 1.1:!.52 12 9.80 1.1134 13 9.60 1.1083 14 9.40 1.0933 15 9.~0 1.080.5 16 9.00 Ulli6:! 17 8.80 1.0663 18 8.60 I 0697 19 8.40 1.07.52 20 8.20 1.07.57 21 8.00 10792 22 7.80 1.0822 23 7.60 1.0827 24 7.-W 1.01140 25 7.:!0 1.0847 26 7.00 1.084~ 27 6.80 J.OBOS 28 6.60 1.0787 29 6.-W 1.0778 30 6.20 1.0713 31 6.00 1.067.5 32 .5.80 1.0636 33 .5.60 1.0604 34 .5.40 1.0607 35 s.~o 1.0760 36 s.oo 1.0897 37 480 1.1047 38 4.60 1.1207 39 440 1.13.56 40 4.20 1.1493 41 4.00 1163.5 42 3.80 1.1811 43 3.60 11997 44 3.40 1.2174 45 3.20 1.2340 46 3.00 1.2498 47 Z.80 12648 48 2.60 1.29.58 49 2.40 1.3321 50 2.20 1.3677 51 200 1.4039 52 1.80 1.4397 53 1.60 1.4746 54 1.40 1..5088 55 1.20 1..5423 56 1.00 1.5120

• 57 080 1.0000 • 58 0.60 1.0000 • 59 o . .ro 1.0000 • 60 0.20 1.0000 • 61 0.00 1.0000

* Top and bottom S axiaJ points excluded per Terhnh:al Sperlftcation 83.2.1.

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JULY2015

Page 10 ofl5

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I '••

CORE OPERATING LIMITS REPORT. FNP UNIT l CYCLE 27

c 1: l! 'D .c i Ill a. s ~ c 0 :e Ill 0 a. ~ c Ill m !

Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power

Fully Withdrawn - 225 to 231 steps, inclusive

225 I I t ~ (.552, 226) .- I

~ ! ~ .

200 lot

~

175 ~

~"' Banke -

150 ~ +f-"' I

;

" , 125 ~

I 1- ; (0,114) ~

~

100 ~

1~ . Bank D I

76 ~ ! , , -~

50 ~ II'"

~

1-1- . !; ~ 1-25

I" ,1' , (.070, 0)

0 0.0

,. 0.1

I I I I I I

0.2 0.3 0.4 0.6 0.6 0.7 0.8

Fraction of RATED THERMAL POWER

JULY2015

I

(1,187) = ;

~

~ ,., l

1-

0.9 1.0

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, B, C, D and a control bank tip-to-tip distance of 128 steps.

Page 11 of IS

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27 Jl1LY2015

Figure2 K(Z)- Normalized FQ(Z) as a Function of Core Height

1.2

1

-~ 0 -u ca 0.8 u.. Q c

:iii! ca -CD D.

i 0.6 .~ ii e 0

Core Height (ft.) K(Z) -- - 0.000 1.000 z 6.000 1.000

I -N 12.000 1.000 - 0.4 :.r::: I

I I

FQ= 2.50 I

0.2

- -

0 0 2 4 6 8 10 12

Core Height (feet)

Page 12 of 15


120

110

100

90 ii 1&1

~ 80 _, c(

70 :e a: 1&1 :1: ... 60 Q

5 so .... 0

!. .. 40 I a. 30

20

10

0

Figure3 Axial Flux Difference Limits as a Function of

Rated Thermal Power for RAOC

r (-12,100) (+9, 100)

' -- ·-'- v _) UNACCEPTABLE j ~ o.~E RAJ IOJ 1

I \ I r -~ ~ ACCEPTABLE

OP RAJ10~

J ' I \

.--UNACCEPTABLE

.OPE tAT ON I--

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

-60 -so -40 -30 -2o -1o 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %

Page 13 of15

CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 27

680

-lo....

I c..

640

f.-

IX...

600

680 f.-

660 0.0

1- -

"' t.... r" ~

j'... ~ t-...

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

i .......

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

-

r l

0.2

Figure 4 Reactor Core Safety Limits

UNACCEPTABLE I OPERATION

"-"""" ~ ~

"' ~ 1'--. r--...~

......... ....... !-.... j'... ....... ["'-.

~ ...... ........ ["'-. ~ ...... - ....... r--... ' r..... t-... -

~ ....... ! I"'> ....... ....... ....... r.....

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

["'-. ....... ........ .....

........ 1'--r---.. ~

ACCEPTABLE t OPERATION -

-

f-

--- i -

0.4 0.6 0.8

Power (Fraction of RATED THERMAL POWER)

I

....... ~ ~

...... I"'> j'...

......... r....... ........

~ r---..

1.0

-

\ \

._

........

......

-

\ \

\

!.......

~

--

JULY2015

.....,)-- 2421 pslg

-o- 2235 palg

-..r-1981 pslg

-x-1821 palg

1.2

Page 14 of 15


. FigureS PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

;; 0

l "" ; •rl 0 ·rl

:tl .. 8

-24. 0

' CD -24.5

~

I ~ .. I

-25.0 16000

' ' ' !' ~ "' ' "'-' '- ' ' "" ~ ~

' ' 17000 18000 19000

Cycle Burnup (MND/MrU)

Cyc1eBmnup (MWDIMTU)

16000 17000 18000 19000 20000

Moderator Temperature Coefficient (pcm/°F)

-24.12 -24.34 -24.58 -24.77 -24.95

JULY2015

'-

' 20000

Page 15 of15



Enclosure 2

Farley Unit 2 Cycle 24 Core Operating Limits Report Version 2

':- 1 ,


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 ofTechnical Specification 5.6.5.


13.I.I SHUTDOWN MARGIN- MODES I and 2 (with kerr~ I)


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 Temperatw'e 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:'n 3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT

(OPAT) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperatw'e, and RCS

Total Flow Rate 3.9.1 Boron Concentration

Page I of 15



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 ksJr > 1.0) (Teclmical Requirement 13.1. l)

2.1. l The SHUTDOWN MARGIN shall be greater than or equal to 1. 77 percent Aklk.

2.2 SHUTDOWN MARGIN- MODES 2 Cwithkgr< 1.0). 3. 4 and S (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 Aklk.

2.2.2 Mode S - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Aklk.

Page 2 of 15




The BOUARO-MTC shall be less than or equal to +0.7 x 104 Ak.lk/"F for power levels up to 70 percent RTP with a linear ramp to 0 Aklk/°F at 100 percent RTP.

The EOUAROIRTP-MTC shall be less negative than -4.3 x 10-4 Aklk/°F.


The 300 ppm/AROIRTP-MTC should be less negative than or equal to -3.65 X 104 AkJk/°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 bumup corresponding to the measurement of 300 ppm at RTP conditions, •• AFD Correction is the more negative value of:

{0 pcmfDF or (MFD • AFD Sensitivity)} where: MFD is the measured AFD minus the predicted AFD from an

incore flux map taken at or near the burnup corresponding to 300ppm, AFD Sensitivity = 0.07 pcmi"F I MFD

***Predictive Correction is -3 pcm/°F.

The I 00 ppm/ AROIRTP-MTC should be less negative than -4.0 x I 04 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


.. 1:.:. 4.:,. • , ..... ,.~ ,;~ ~· ·, • • ' I '0 I '


.............. - ... \...t n ••• ... . '

Page 3 of 15

•. ~ J • ~. • - • ..- I ,• ~ , ....... - ........... It~ ....... -~ .... ,, .. -- ... ~- .. -,. .. ·~-- ............... t ............. ·~·· ,.\ •• -. ........ -.\-

' 0 'I 0

1

I'~ ~- "' ~ 0J ~ _. 0

\ l \ o 0 0~ l 1 ""I ~ , "' I 0

It i, • •

:;~ ..... .,.'!a.~··,~ ..... 'f ~ . .. .. . ' .



2.5 .I The control rod banks shall be limited in physical insertion as shown in Figure I.

2.6 Heat Flux Hot Ch8nnel Factor- F0 (Z) (Specification 3.2.1)

F,RTP 2.6.1 FQ(Z)~-Q-•K(Z) p

F,RTP FQ(Z)~-Q-•K(Z)

0.5

forP>0.5

for P~0.5

where: P THERMAL POWER RATED THERMAL POWER

2.6.2 F;TP =2.50


2.6.4 F:RTP *K(Z) F. (Z) < _Q:..,.._ _ _;__

Q - P•W(Z) FQRTP •K(Z)

FQ(Z)~ O.S•W(Z)

forP> 0.5

forP~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 F0 (Z) penalty factors are provided in Table I.

Page4 of15

--'--¥~-

~· ·'" ·'""~;~··· .... · -• ~~ •-· '"'·- :.. .,; . .,. :-~.7 ·::: :·, -; , :: :· -6"' 4':":..: · ~ ••... ;. ,~· w- -:-::~::·.::-: .. : -:·:·.-r :",, ...... ~ :~:·· h .. ~-"7,,


2.7 Nuclear Enthalpy Rise Hot Channel Factor- F~ (Specification 3.22)

2.7.1

2.7.2

2.7.3

F~ s F;;;P *(I+ PF~ *(1-P))

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

PFM =0.3


2.8.1 The Axi~ Flux Difference (AFD) acceptable operation limits are provided in Figure 3.



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 Trio System Instrumentation Overtemperature d T COT d T) and Overoower d T COPdD Setooint Parameter Values for Table 3.3.1-1 (Specification 3.3.1)

2.11.1 The Reactor Trip System Instrumentation Overtemperature d T (OT d T) and Overpower dT (OP6T) setpoint parameter values forTS Table 3.3.1-1 are listed in COLR Tables 2 and3.

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 press~. 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 minimwn 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 ofkcrrs 0.95 (all rods in less the most reactive rod) and subcriticality (ml rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.

Page 5 of 15

ll ' ~ • • . • ' e I o • I \ ,. ,. ,..,... ll I" I >J1 .. -~~' ... .,.._...,_"'. "> ······~~ f •• ' 0 -j • f ... •'- l•

·, , ..... ".. .. ,.\ ·' ..... ·...:...._·~---·~~~~-- . . .' ... _:.,. ,_:: • 11' ....... I' t ... ·~~


Tablet

FQ(Z) Penalty Factor

CyeleBumup FQ(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 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 bumup at which the FQ(Z) was detennined.


3. For all cycle bumups outside the range of the table, a penalty factor of 1.0200 shall be used.

Page 6 of 15

..

.. • , I 1 1 ~ • & 1 , • ,. ' • •- •

'9 ............... _ ... ..,, .... - ......... '"'1 ~•'!of ,llfll'l. o\1~~ .... ~--: ;• .. 11 01'' ... •'~·::-J &.J''"'"'""~ 0t~ 0••t¥•,•,•1"• ... ; 1• ~ ..... ~a.-.... _~:~~: ..... ~~ •:;"••o 1 :J-I ~·.-......:",. ~, • ' • • ' • ; ' t' • .....:c•'__,__,_. '-~~--


Table2

Reactor Trip System Instrumentation- Overtemperature ~T (OT~T) Setpoint Parameter Values

P' == 2235 psig

K1= 1.17

t1 2:30 sec t4= 0 sec

fl(M) = -2.48 {23 + (qt- qb)} 0% ofRTP 2.05 {(qt- qb) - 15}

. .

Kg= 0.000825/psi

t6~ 6 sec

when (qt- qb) ~ -23% RTP when -23% R1P < (qt -qb) ~ 15% RTP when (qt- qb) > 15% R1P

Page 7 of 15

. \ r'• P •I"'"" \:' •• ~· ~~ t. 0 H -~:ry•• 0 \uo :..

' r • •' • : _._--'-• ~-•!._'~-

'· ....... -- .. . . . . •, .... - ~~'\"'!'·.·f ... -: .·~ t.-

f • ' .;,.-.,. .... · ... -.~: ......... .,... ........ ,: ... , :"1::; .. -,.

.. ,.. .. ~ ..

r" ... _ ........... ,." .,_ ' ..


Table3

Reactor Trip System Instrumentation- Overpower .1.T (OP.1.T) Setpoint Parameter Values

1<4=1.10 Ks = 0.02;oF for increasing Tavg Ks = 0 ;oF for decreasing Tavg

1<6 = 0.00109 ;oF when T > T" 1<6 = o;oF when T ~ T''

T3~ 10 sec T4= Osee TS~ 6 sec T6~ 6 sec

f2(Al) = 0% RTP for all AI

""''' ,~ •• ,_.~ _., • .,..:~ .. ""' ..... :;..~.·-·~ ""} .... ~- ,,,., ••""'.. : ••••• ..,.. ~ ~tr•_.""\~ '~'"I· .•.•• .':, •. ~.w .. t ... .... . ~ '' :.:~· ·--~-~ -·-'--'-'· '-' --'·-·--··"-----'-' ~---~' ·~·,~' ., ..

Page 8 of 15

, ,·'"' !

...... • ........ • .... ., - -;:t -· .... !•••· ' ' ,•, "'- "

......... t"~:l!lo< ._ ''~ .......... . ..

• ~

• • •

• • • • •


AslaiPolat 1 2 3

' 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 2& 25 26 '0 28 29 30 31 32 33 :M 35 36 ~

38 39 40 41. 42 43 44. 45 46 ~ • 4!}

so 51 52. 53 M 55 56 Sl 58 59 60 61

•

Elevation (feet) 150 MWDIM11J 12.00 1.0000 11.80 1.0000 11.60 1.0000 1140 1.0000 11.20 1.0000 11.00 1.1235 10.80 1.1213 10.60 1.1162 10.40 1.1110 10.20 1.1051 10.00 1.1110 9.80 1.1143 960 1.1167 9.40 I. IISS 9.20 1.1186 9.00 1.1183 8.80 I.ID 8.60 1.1374 8.40 1.1502 8.20 1.1611 8.00 1.1702 7.80 1.1767 7.60 1.1810 7.40 1.1838 7.20 1.1843 7.00 1.1832 6.80 1.1805 6.60 1.1766 6.40 1.1713 6.20 1.1649 6.00 I.IS7S 5.80 1.1495 5.60 1.1416 5.40 1.1443 5.20 1.1576 s.oo 1.1693 4.80 1.1807 4.60 t.l915 4.40 1.2016 4.20 1.2105 4.00 1.2184 3.80 1.2256 3.60 1.2316 3.40 1.2383 3.20 1.24SS 3.00 1.2607 1.80 1.2833 1.60 1.3061 2.40 1.3283 1.20 1.3499 1.00 1.3771 1.80 1.4053 1.60 1.4316 1.40 1.4563 1.20 1.4791 1.00 1.4995 0.80 1.0000 0.60 1.0000 0.40 1.0000 0.20 1.0000 0.00 1.0000

Table4 RAOCW(Z)

3000 MWDIMTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.1452 1.1446 1.1391 1.1330 1.1316 1.1212 1.12!10 1.1286 1.1264 1.1231 1.1188 1.1121 1.1085 1.1167 1.1267 t.l349 1.1410 1.1454 1.1487 1.1501 1.1510 1.1SOB 1.1497 1.1474 1.1440 1.1399 1.1352 1.1308 1.1411 1.1519 1.16'22 1.1719 t.IBII 1.1895 1.19119 1.2034 1.2097 1.2110 1.2240 1.2301 i2339 1.2410 1.2651 1.2868 1.3134 1.3401 1.3662 1.3909 1.4140 1.4354 1.4546 1.0000 1.0000 1.0000 1.0000 1.0000

10000 MWDIMTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.2675 1.2602 1.2390 1.2244 1.2219 1.21!18 1.2244 1.2251 1..2275 1.22S3 1.2342 1.2365 1.2403 1.2535 1.2642 1.2726 1.2772 1.2791 1.2190 1.2750 1.2682 12594 1.2491 1.2366 1.2223 1.2067 • 1.1904 1.1753 1.1689 1.1682 1.1680 1.1668 1.1645 1.1611 t.l569 1.1519 1.1453 1.1310 1.1300 1.1245 1.1219 1.1276 1.1316 1.1413 1.1574 1.1667 1.1758 1.1851 1.1945 1.2038 1.2129 1.0000 1.0000 1.0000 1.0000 1.0000

Top and bottom 5 ulal polats ndaded per Technical Speclfitatlon 83.2.1 •

.-~.~!: .. "':\~,:~ _, ·.=· .. ~· ... ~···,•·.to( of•""- ..... r·····~-""--t••"'·-- '""\ ._..., _ ____. __ __; __ ~_·_~_.__,_, __ ~··~~----'---'-------~~ ",: ~ 4of ,, I

JULY2015

14000 MWDIMTU 18000 MWDIM111

, .• -"'"• r.:"' ..... ..

1.0000 1.0000 1.0000 1.0000 1.0000 10000 1.0000 1.0000 1.0000 1.0000 1.2613 1.2.533 1.2.522 1.2426 1.2332 1.2206 1.2146 1.1961 1.1933 1.1846 1.1958 1.1779 1.2012 1.1701 1.2015 1.1631 1.20!17 1.1611 1.2226 1.1712 1.2314 1.19111 1.2357 1.2210 1.2372 1.2543 1.2464 1.2779 1.2622 1.2979 1.2747 1.3151 1.2834 1.3277 1.21195 1.3370 1.2!137 1.3441 1.2!135 1.3460 1.2909 1.3437 1.2870 1.3389 1.2814 1.3320 1.2732 l3221 1.2628 1.3094 1.2506 1.2947 1.2374 1.2789 1.2223 1.2ti07 1.2088 1.2412 1.2082 1.2ml 1.2064 1.2339 1.2036 1.2306 1.1991 1.2251 1.1932 1.2177 1.1860 1.2088 1.1776 1.1984 1.16n 1.1849 1.1539 1.1681 1.1450 1.1523 1.1381 1.1344 1.1310 1.1390 1.1463 I.ISS6 1.1606 1.1109 1.1743 1.1868 1.1882 1.2027 1.2008 1.2170 12128 1.2306 1.2250 1.2446 1.2313 1.2591 1.2494 1.2735 1.2613 1.2879 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

Page9 of15

' . . ,. ~~· ~-.,.. t:'"",4 to , ... ,_..~#o I •,, - ·~· ,., VI '1o. •

,.• o ... ·' • .}< : ~ ' I J~ o fo

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 JULY 2015

Table 5 Part Power (48%) RAOC W(Z)

Axial Point Elevation (feet) ISOMWDIMTU • 1 1~.00 1.0000 • 2 II 80 1.0000 . 3 11.60 I 0000 • 4 II -10 1.0000 • 5 II~~~ I ((100

6 II 00 I ~173 7 lO KO I 2(1)8 8 10.60 1.1857 9 10.-10 11663

10 10.20 1.1453 11 10.00 1.1357 12 9.80 1.1232 13 9.60 1.1086 14 9.40 1.0916 15 9.~0 1.0817 16 9.00 1.0694 17 8.80 1.0620 18 860 1.0701 19 8.40 1.0762 20 8.20 I 0818 21 8.00 1.0865 22 7.80 1.0900 23 7.60 I 0924 24 7.-10 1.0943 25 7.20 1.0949 26 7.00 I 0946 27 6.80 1.0926 28 6.60 1.0862 29 6.40 I 0813 30 6.20 1.0783 31 6.00 1.0740 32 5.80 I 0699 33 5.60 1.0673 34 5.40 1.0754 35 520 1.0936 36 500 1.1104 37 4.80 11271 38 4.60 I 143~ 39 4.40 1.1587 40 4.20 I 1728 41 4 00 11860 42 3.80 I 2001 43 360 1.2131 44 3.40 1.2269 45 3.20 1.2410 46 3.00 1.2630 47 2.80 1.2925 48 2.60 1.3224 49 240 1.3508 50 2.:!0 1.3790 51 2.00 1.4152 52 1.80 14522 53 1.60 1.4869 54 1.-10 I 5202 55 1.20 I 5515 56 1.00 I 5805

• 57 0.80 I 0000 • 58 0.60 I 0000 • 59 0.-10 I 0000 • 60 0.~0 1.0000 . 61 0.00 1.0000

• Top and bottomS axial points excluded per Technical Specification 83.2.1.

Page IO of 15


c J: l!

"CC .1:

~ Ill ICL • ~ c 0 E Ill 0 a. ~ c Ill

CD

!

Figure l Rod Bank Insertion Limits versus Rated Thennal Power

Fully Withdrawn- 225 to 231 steps, inclusive

225 ~~ r- (.552, 225)

~

200

" -, ~

175 ~ 1.;'

~

Banke

150 ~ , ~ ,

~

125 ,

I . 1.;1' (0, 114) ~

100 1-

" , BankO ., 75 r-· " - -IL

r-.,

50 f-· ~ , r-r--f--1--

~

25 , -

~ , , (.070, 0)

0 0.0 0.1

I I I I I

0.2 0.3 0.4 0.5 0.6 0.7 0.8

Fraction of RATED THERMAL POWER

JULY2015

(1, 187)-I

1.11 ~

1.11 ~

1-r-

0.9 1.0

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 I 28 steps.

Page II of IS


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

1.2 I

1

-... ~ Cl 0.8 IL CD c :i! Cl CD a..

1 0.6

- ~ ·-

'ii ! 0 z

Core Height (ft.) K(Z) 1-- 0.000 1.000

6.000 1.000 -N 12.000 1.000

~ 0.4

FQ=2.so- -

0.2

-

0 0 2 4 6 8 10 12

Core Height (feet)

Page 12 of 15

' . .. .. "' : ... ~..,...,. . ' ,J • • , . r,~,- ... .., . ·:~ ........ .:~., .. .., ... ..., ,'-... ., ...

. ''

. . .

CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 24 JULY20IS

120

110

100

90 iC Yo!

~ 80 _, c 70 :E a: Ill :z: .... 60 Q Ill

5 50 .... 0

!. .. 40 i

D.

30

20

10

0

1--'

Figure3 ADal Flux DifTerence Limits as a Function of

Rated Thermal Power for RAOC

(-12, 100) (+9, 100)

- v UNACCEPTABLE 1 ~ I _ lPERA1Jot I \ J

v , -;ccEPTABLE \ __ OPERATION

J ' v \

l UNACCEPTABLE ,...-

L q~~IQN

(·25, SO) (+24, SO)

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

Page 13 of IS


680

lo.... 660

Ia...

640

..

I~

600

680 1--

660 0.0

:--.... .....

........

' r-.....

'

1--·

........ ~

r-.....

' :--..... '

I I

-

0.2

Flgure4 Reactor Core Safety Limits

UNACCEPTABLE OPERATION

r-..... ....... r...... r...... "-f--1--

r...... r-..... r--.... ' ' " r--.... :-...... f""-.. :-...... "' ........

~ r-..... "-

' ........ r-..... ......

r-..... ........ r...... r-..... ..... r...... ~ .......

!':-..... ...... r-..... r....... r........ --...... ...... ........ r..... r-..... .......

........ r.......

....... ......

f"... !'--.. - - . . - -r-..... '"' ACCEPTABLE I OPERATION I

--

- -

0.4 0.6 0.8

Pow.r (Fraction of RATED THERMAL POWER)

ruLY2015

I I

-

- - 1-

""" ........ ""0

~ ->- 2425 pslg

\ !'...... -o- 223& pelg

........ ........ \ !---

-.l-11811 pelg

[\ -x-18211 pslg

\ r....... ........

~ !'--.. r.....

r-..... t--..... !'-..

--

1.0 1.2

Page 14 of15


FigureS PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

r; 0

l i

-23.5

""f"'oo-,

·a -24.o ... l u

~ • ... i -24.5

if

~ Ill

t -25.0

15000

....... I' t'-

!" ~ ""I' ~

""'"" ~ """" r" """" I"'

16000 17000 18000 Cycle Burnup (MWD/MTU)

Cycle Burnup Moderator Temperature (MWD/MTU) Coefficient (pcmfOF}

15000 -23.79 16000 -23.98 17000 -24.16 18000 -24.33 19000 -24.53

JULY2015

~ ""

19000

Page 15 of 15



Enclosure 3

Vogtle Unit 1 Cycle 20 Core ·operating Limits Report Version 1

... • ,. ~,.,. ~·- rr oM. \:..,..

' ' '

' •. ~ I 1

• •• -~ .. ~",f"""*•f"'J o :-•••"':""": I .. ,·- 'f .... ~

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 20 JUNE2015


This Core Operating Limits Report (COLR) for VEGP Unit I Cycle 20 has been prepared in accordance with the requirements of Technical Specification 5.6.5.


13.1.1 SHUTDOWN MARGIN- MODES I and 2


3.1.1 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 3.9.1

SHUTDOWN MARGIN - MODES 3, 4 and 5 Moderator Temperature Coefficient Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor - FQ(Z) Nuclear Enthalpy Rise Hot Channnel Factor- FN AH

Axial Flux Difference Boron Concentration

Page 1 of13

,. . . . ' ' . ' .,,. ....... .,1 .,.. ,,-........,•...._· • ., .... ,..,. •• ,. .•• ,.~.,..,. •t.•-• •""· ... ,..~ ........... ~ , ..... """! .. ,;•·.., v; ....... , .... ;\·~'•., '""'•,'',.'' '''\" • • ""''; • .-... .... ~ ... ·:-. rj' .. '•': ....... ·-•

• r\ ! ... t .. • ' • , •• ) • • lo "I ~ • :-•

CORE OPERATING LIMITS REPORT. YEGP UNIT 1 CYCLE 20 JUNE2015


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 (Technical Requirement 13.1.1)

2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent L\k/k.

2.2 SHUTDOWN MARGIN- MODES 3. 4 and 5 (Specification 3.l.l)

2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.

Pagel of13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 20 JUNE 2015



The BOLIAROIHZP-MTC shall be less positive than +0.7 x 10 ... ~klk/°F for power levels up to 70% RTP with a linear ramp to 0 ~klk/°F at 100% RTP.

The EOL/ARO/RTP-MTC shall be less negative than -5.50 x 10,.. ~F. 1


The 300 ppm/AROIRTP-MTC should be less negative than or equal to -4.75 X 10-4 ~klk/°F. 1

The revised predicted near-EOL 300 ppm MTC sha11 be calculated using Figure 6 and the following algorithm:

Revised Predicted MTC = Predicted MTC• + AFD Correction"'* + Predictive Correction•••

where, • Predicted MTC is calculated from Figure 6 at the bumup corresponding to the measurement of300 ppm at RTP conditions, .,.. AFD Correction is the more negative value of:

{0 pcmrF or(MFD • AFD Sensitivity)} where: MFD is the measured AFD minus the predicted AFD from an

incore flux map taken at or near the bumup corresponding to 300 ppm, AFD Sensitivity = 0.08 pcm/°F I MFD

•••Predictive Correction is -3 pcmrF.

The 60 ppm/ARO/RTP-MTC should be less negative than -5.35 x 10 ... ~F.1

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER

1 Applicable for full-power T -average of 584.1 to 587.1 °F.

• • 1 , ..

Pagel of13

'.,1-vr"~: "".~ .. , •,a' t ,~ ........ '-11 • "" .. .... . .. ,,."' .... , ... -... -.• '• '! r

··"·"' -a': t. • : .1' : ... ~· .... ;-:-' • ~ .. ~ A,... ._ ·, • • I • .: •

:.,:: .... ,. , ..... ....-.: ............... , ...... ~"'. : .. ~ ... ~:. .. .. , ..... . , , .. "1: • ·~

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 20 JUNE 2015




2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 3.

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

F./IT/'

2.6.1 Fu(Z) s-<:-1 -· K(Z) for P> 0.5 p

2.6.2

2.6.3

2.6.4

F.R71'

F{.)(Z)s-"-1 -·K(Z) forPS0.5 0.5

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

K(Z) is provided in Figure 4.

F.RTI'. K(Z) F (Z) S <! for P > 0.5

" P·W(Z)

F.RTI' • K(Z) F. (Z) < (] for P :S 0.5

(] - 0.5 ·W(Z)

2.6.5 W(Z) values are provided in Table 2.

2.6.6 The FQ(Z) penalty factors are provided in Table I.

... a.' ... ,. , • '. • ~ ~ .......... -~t'*., .,._ ........ -~- .. -~ ..... _ .. ·.:..·-. .;._ . . ·:" ......... ;~----·· """'"''i ~ ................ -; ... - ..... ~-~(( ...... ~ ,,~·'!,"'' , .... '11 :"'" .... ~ -: . . '. i· !' •.. ---~----~-'·'-----·-· ---'-~~....___ ~----'"~-~

Page4 of13

'•• • ....,._.... .,. _,., t• • •.• ... •• -t

........ . .


2.7 Nuclear Enthalpy Rjse Hot Channel Factor· FN t.H {Specification 3.2.2)

2.7.1 F~ sF:;:'· ·(1+PFLVI ·(1-P))

where: P THERMAL POWER RATED THERMAL POWER

2.7.2 F:;J1' = 1.65

2.7.3 PFt.H =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 5.


2


This concentration bounds the condition of !cars; 0.95 (all rods in less the most reactive rod) and subcriticality (1lll rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and 8 10 deplet~on.

PageSof13

"' ' , . ~ ..... - '""",):· llo - ,... ••• -tll.i, • .,: ... ~ ~ .,. ....... .. ~ .

' • ,.: .. ,.~.·~• .-.- -·~• •· T 14 ~ ~~---11• • I ~ I> " 'ff (

_.,h .'• .: •.. ·-~ ... ~ ......... : ... / ... ;. •-:'--:."::·~·-·~···.~··. . --~--~----- -·~-~~-·--

..... "':' •• 1 • . ..


Tablet FQ(Z) PENALTY FACTOR

CycleBumup FQ(Z) Penalty Factor (MWD/MTU) 368 1.0200 585 1.0265 803 ).0362

1020 1.0391 1238 1.0397 1456 1.0390 1673 1.0373 1891 1.0325 2108 1.0265 2326 1.0204 2543 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 bumup 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 1.020 shall be used.

Page 6of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 20 JUNE2015

Tablel RAOCW(Z)

- Asial Elevation 150 4000 12000 20000 Pol at (rftt) MWD/MTU MWDIMTU MWDIMTU MWD/MTU

1-5 11.071-11.167 1.0000 1.0000 1.0000 1.0000 6 11.066 1.2119 J.JI65 1.1"757 1.1190 7 10.165 1.1170 1.3119 1.1715 1.1195 I 10.664 1.1663 1.3741 1.1616 1.1031 9 10.461 1.1531 1.3609 1.1494 1.1115 10 IO.Z61 1.1461 1.3381 1.1366 J.l711 II 10.060 1.1191 J.lll9 1.1110 1.1731 11 9.859 1.1197 1.1875 1.1047 1.1759 13 9.651 1.1119 1.1619 1.1871 1.1791 14 9.4!16 1.1197 1.1497 1.1111 1.1134 15 9.155 1.1101 1.1500 1.1716 1.1155 16 9.054 1.1199 1.1453 1.1791 1.1904 17 1.153 1..1305 1.1351 1.1797 1.1035 II 8.651 1.1319 1.1167 1.1107 1.1171 19 1.450 1.1315 1.1171 1.1- 1.1113 10 8.149 1.1333 1.1096 1.1944 1.14011 11 8.048 1.1390 1.1016 1.1987 1.1518 21 7.847 una 1.1961 1.1011 1.1634 13 7.646 1.1411 1.1941 1.1014 1.1753 14 '7.444 J.ll84 1.1193 1.1806 1.1846 15 7.143 1.1317 1.1817 1.1966 1.1117 26 7.0ol1 1.1150 1.1711 1.1904 1.1889 17 6.841 1.2157 1.1615 I.IW 1.1169 21 6.640 1.1041 1.1491 1.1757 1.1811 19 6.438 1.1916 1.1368 1.1689 1.1749 30 6.137 J.l791 1.1330 1.1611 1.1648 31 6.036 1.1681 1.1193 1.1546 1.1518 31 5.835 1.1593 1.1147 1.1463 1.1414 ll !1.634 1.1498 1.1199 1.1459 1.1337 34 5.431 1.1413 1.1193 1.1514 1.1191 35 5.131 1.1443 1.1159 1.1601 1.1194 36 5.030 1.1481 1.1348 1.1669 1.1194 37 4.819 1.1511 1.1430 1.1711 1.2197 38 4.618 1.1536 1.1509 1.1176 1.1111 39 4.416 1.1565 1.1511 1.1814 1.1159 40 4.115 1.158!1 1.1646 1.1848 1.1114 41 4.024 1.159'1 1.1705 1.1859 1.115!1 41 3.813 1.1599 1.17!16 1.1859 1.1069 43 3.621 1.1607 1.1798 J.IDI 1.1951 44 3.410 1.1645 1.1837 1.1931 1.1874 4S 3.119 1.1616 1.1850 1.1957 1.1804 46 3.011 1.1704 1.1968 1.1033 1.1837 47 Ul7 1.1117 1.2169 1.1177 1.1961 ... 2.616 1.19111 1.1373 1.1321 1.21116 49 1.414 1.1113 1.1599 1.1476 l.l111 50 UIJ 1.1164 1.1835 1.1613 1.1336 Sl 2.011 1.2416 1.3069 1.1759 1.1443 51 1.811 1.156!1 1.3301 1.2119 1.1543 53 1.610 1.1706 1.3511 1.3015 1.1649 54 1.401 1.1841 1.3719 1.3136 1.2760 5S 1.107 U971 l.l924 J.J151 1.1871 56 1.806 1.3093 1.4100 1.3359 1.1985

57-61 0.105-0.000 1.0000 1.0000 1.0000 1.0000

Top aod Boltom S Poinls Euluded per Technical SpeeiOcatlo• BJ.2.1.

These W(Z) values are consistent with Figure 5, and are valid over the HFP Tavg temperature range from 584.1 to 587.1°F.

Page 7 of13

- ..... " .!., ...... ~ • "" - ... ""..:... ..

-'-"-·'----···--=-_..1 • .... ·- · --~-~~-


FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND

VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING)

5.0

4.0

1.0

0.0 0

ACCEPTABLE OPERATING REGION

(2 00, .1 P> .,;"""

v v v RE:lUIRED SHUTDOWN MARGIN v k""

(1 00, .2 ~) v v v L

v v ~ v

!UNACCEPTABLE OPERATING REGION I c ~sc, • ~ 0)

500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

PageS of13

CORE OPERATING LIMITS REPORT. VEGP UNITt CYCLE 20 JUNE2015

FIGURE2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND S (MODE 4 WHEN FIGURE 1 NOT

APPLICABLE)

..... ~ ..... ~ riP -t.r; H t!l

a

I til •

5.0

4.0

3.0

2.0

1.0

0.0 0

(2 00, .9 ~ v

.L

v V"

""v v" !ACCEPTABLE OPERATING REGION I

'/ .L

v " v L v !REQUIRED SHUTDOWN MARGIN~ (~ 50 , . .8 j))

v v v v

v I UNACCEPTABLE OPERATING REGION

,I

( ~6( , .(] 0)

500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page9of13

CORE OPERATING LIM ITS REPORT. VEGP UNIT 1 CYCLE 20 JUNE2015

FIGUREJ ROD BANK INSERTION LIMITS VERSUS% OF RATED THERMAL POWER

. . (Fully W1thdrawn )

220

200

1180

:g ~ 160 a: Ill Ill ~ 140 IUl

~ 120 H E-t H IUl g 100

a 80

§ 60

40

20

0 0

~

1/

1/ v

BANK B 1/

~

:1:111 ,til

v v v

I ..I

I/ II'

ltlllll ol.liti I)

( 5 • "''IS

10 20

I ( lOlls 1212 5 ~ v

1/ 1/

1/ v

I ..I BANK C I ..I 1/

1/ ~

~

1/ BANK D 1..1 /

~ ~

lJ ,) ..1

30 40 so 60 70 POWER (\ of Rated Ther.mal Power)

1718 ~~

I (

1/ 1/

~

80 90

• Fully withdrawn shall be the condition where control rods are at a position within the interval ~ 225 and !!> 231 steps withdrawn.

IZ ll

1

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 II S steps.

0

Page 10ofl3

• .... a, ._.,......,.t_• . t ,,. ••:.,:t ... ~ • ~· ••·-~·-,.i.~. • • ;..lr.' r "~ ,'

. .; . . . . . . ~ ~~· ~"'' ·- ...... ,_ ......... , ....... ,, .... ·-··· ....

• ' • , rl • t • " \. ' .·

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 20

FIGURE4 K(Z)- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT

1.4

1.2

~ ~ 1.0

~

a Pi 0. 8 il N

i ~ 0.6

..... N

~ 0.4

0.2

0.0 0 2

FQ = 2.50

CORE HT. K(Z) ---- ----0.00 1.00 6.00 1.00 12.0 .925

4 6 CORB BBIGBT (feet)

' I ~ • ~ I 1 t

,._ •• oa.-,:7 ~ / 't. -~~ .. .-~ ...... :' .. lo,. ~·. ~ .. ~-•IJ. •' '' "'41"( ~ .,., • --"""I •• -:-J ';"'"' .... ~ • -'. J • I,. ( • • : 1 •' I" l ~ 0

.. ,. : t .• f ' ..... ' I I ~

8 10

JUNE 2015

12

Page 11 oflJ

. ,. '· . . . "" , , ·~ l"f' "· .. • ,..,., r ., .,. • - ( ~,. ..

f. • • ' • • ~I ~ ' ,. .. • •

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 20 JUNE2015

FIGURES AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF %RATED THERMAL POWER

FORRAOC

..... 1-1 CD

~ g.

.... a CD ~ E-t 'lj

CD .aJ Ill PI IN 0 rll' .... PI

~ g.

120

110

100

90

80

70

60

50

40

30

20

10

0 -so

u fmc EP'

II (-30,

-40

(-15, 100) (+10, 100)

I \ :AB E I \ UNl CCI PTJl

II \ \

I \ I A~CE PTA! LE \

IJ \

I \ I \

I 1\

50) I (+26, 50)

-30 -20 -10 0 10 20 30 AXIAL FLUX DIFFERENCE (percent AI)

;..· .• .. :.: . ... :.~ .. :·:.,",""h" .. , .. ~ ... : ..... :·.'·;·-.. ~:;~:~· 1".·: · .. ·:. --''--'"""~·...;."'--

BLE

40 50

Page 11 oflJ

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 20

FIGURE6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-2 7.5 .,....,r-r--r-r-T....,-T"'T..,....,....,r-T"-r-r-T....,-T"'T..,....,....,...,..-r-r-T....,-T"'T.....--.

~ ~ -l -- ~~ _:_ ~~~-~ .. ,_ = ~- ~- :- = --·~- - ~ ~ ·· ~~!- - ·r-~ · -r-- - - · - t-r-·r- - - - -1- - r--

t -28.0 -H-r-t---t~--t-~i'-~-:--+t--+-t---•1-+-+ .,-~- +-. -t,.--t---+-1· -t-__ -t_-+_ ·+r+·+--+-- 1-+.-i -r--t--t_-'_H ..

-l '1·-- t- -'1"""1::--- r- ···- - ----· - - t-- · . --- - r----1---j--· ', -- ·- 1- - - - · - - - r-·r--· 2 . . -.. .. - [""''I"""' ·- . - - 1- r- - . - -r- -~ - _,_ .. ·- · I- r- ~ - . - - -~ -28.5 +-i-t--t-1-+-i-H--t-+-i-t-+-~:+-H--t-+-i-t-+-t-++H-H 8 · j-1· - --·-- ---- · ~, r · · ·· 1- - -- - -11! . - - - r- ·- - - - - - -- -~~ . .. -- - -~ --j;-· - - -r· -·- ··· (lo.l"ii _._ - ·- -- ~ -15 ·· · - 1 +--· · -·- · · · 1·- - - r - ~ '" · ~ - --i -29.0 ~ :-- - .:.1. - - - 1-- . - ·- - 1- - -r- -- ~ .,._r- - -~ _ , _ • . - - . . . -- 1- • - . --~~ .. i i-- - . - . - . - --1- . . ·- -- . - ·- - ·- . - · '

~-29.5 ; · - - - ·· I-f-- - ·· I- - - - --- - r--

_-it-f~l- ' ~· - --~~ =- -~~-~---r-:_ -- ·.· _ -~ - t·- .· - r-r::- _ ~ _ :-- --.- - - 1-r- --r-r- ·- ·- . . ~r- . - - r- 1-f-·-r·i +- .. 1--- -H- - -1·- - 1- ·- - .. . . -- - -- - f-- -

-3o.o +-'-'-......... -+-......... '-'-...._,f-'-........,'-'-+-'--'-...._..__......_L..I-...._+-'-_._...._._., 16000 17000 18000 19000 20000 21000 22000

CYCLE BURNUP (MWD/MTU)

Moderator Temperature Cycle Burnup Coefficient (MWD/MTU) (pcmrF)

16000 -27.67 17000 -27.97 18000 -28.24 19000 -28.52 20000 -28.80 21000 -29.04 22000 -29.31

JUNE2015

Page 13 of13

. . . . . .

··. ": : .'i ·~:. '~···.:: "': ': ';" :; 7::' .: ~. -~-" 1 '' .~· •: .;,: :.••. '''"'• ,' ;" ::"~-:: ... ,:i~ .,::,_.-~ ~~"'• :-:<-5.-:·;,., • ..,..,.; -~: ;._ .,..; ~.·•·•."'. ,.:; ~ T .. "·~···.\<• ~\.::-\•:• ~ ·~(~ • _<;

,.



Enclosure 4

Vogtle Unit 2 Cycle 18 Core Operating Limits Report Version 2

' .. '"~ .. \.\ ......... ~· l..:'~"""''

~ .. ' . . . •' ( ·. : 4'.:, ·:,"'~·· : • /'-•. ' ' : ;_-·' ·:.. 0 \ .. H '· f ~ ~ <, • '. ~:.-~·:··· •;• .: ":' ·+'· ,.: ... "',', .,o ...

0 0

.,, ,';.. ~ '----'---~



This Core Operating Limits Report (COLR) for VEGP Unit 2 Cycle 18 has been prepared in accordance ~ith the requirements of Technical Specification 5.6.5.


13.1.1 SHUIDOWN MARGIN - MODES I and 2


3.1.1 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 3.9.1

SHUIDOWN MARGIN - MODES 3, 4 and 5 Moderator Temperature Coefficient Shutdown Bank Insertion Limits Control Bank Insertion Limits Heat Flux Hot Channel Factor - FQ(Z) Nuclear Enthalpy Rise Hot Channnel Factor - FN Ml

Axial Flux Difference Boron Concentration

Page 1 of13



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 and2 (Technical Requirement 13.1.1)

2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent l\k/k.

2.2 SHUTDOWN MARGIN - MODES 3. 4 and 5 (Specification 3 .1.1)

2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and2.

Pagel ofl3

• ~ ,. I



2.3. I The Moderator Temperature Coefficient (MTC) limits are:

The BOLl AROIHZP-MTC shaii be less positive than +0. 7 x I 04 Ak/k/°F for power levels up to 70% RTP with a linear ramp to 0 Ak/k/°F at 100% RTP.

The EOLIARO/RTP-MTC shall be less negative than -5.50 x 104 Ak/k/°F. 1


The 300 ppm/ ARO/RTP-MTC should be less negative than or equal to -4.75 X 104 Ak/k/°F.1

The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 6 and the foiiowing algorithm:

Revised Predicted MTC = Predicted MTC* + AFD Correction** + Predictive Correction***

where, • Predicted MTC is calculated from Figure 6 at the burnup corresponding to the measurement of300 ppm at RTP conditions, ** AFD Correction is the more negative value of:

{0 pcmfDF or (MFD * AFD Sensitivity)} where: AAFD is the measured AFD minus the predicted AFD from an

incore flux map taken at or near the burnup corresponding to 300ppm, AFD Sensitivity= 0.08 pcmrF I MFD

***Predictive Correction is -3 pcmfDF.

The 60 ppm/ARO/RTP-MTC should be less negative than -5.35 x 104 Aklk/°F. 1

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero 11-IERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER

1 Applicable for fuii-power T -average of 583.8 to 586.8 °F.

Page3 of13


2.4 Shutdown Bank Insertion Limits (Specification 3 .1.5)



2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 3.

2.6 Heat Flux Hot Ghannel Factor- F Q(Z) (Specification 3.2.1)

FRTP 2.6.1 FQ (Z) ~ _Q_ · K(Z) for P > 0.5 p

FRTP FQ (Z) ~ _Q_ · K(Z) for P ~ 0.5

0.5


2.6.2 FQRTP = 2.50


2.6.4 F.RTP. K(Z)

F (Z) < Q for P > 0.5 Q - P·W(Z)

FRTP ·K(Z) F. (Z) < Q for P ~ 0.5

Q - 0.5·W(Z)

2.6.5 W(Z) values are provided in Table 2.

2.6.6 The F 0(Z) penalty factors are provided in Table l.

Page 4 ofl3

'• " . '• ·-·~·~-'~ .. ,.:.•, .•. , .... :' .. -........ ,,.,,.,_._ •. ~.&-···· ...... \, J • • • 4. • • ' , • ' ' '' ,.· /r';"'-:-:- ofll, r'l

1 r.o;· ·~ .~,~ & I ~- & '

10

~' ,y.~o-. ~ ,H• t<r~•<t .. '"lf~;:~:-:• ... ~.-• 1 •'11.,.'1 ,'~:'.~ ... 00'f ... ,.,--= ... r,••••''L .. 1 ~~~~'7.,

r • • .. , •-~ '-'-------'---'--~-


2.7 Nuclear Enthaloy Rise Hot Channel Factor- FN m (Specification 3.2.2)

2.7.1 F~ 5.F~JP ·(l+PFAH ·(1-P))


2.7.2 F:;t = 1.65

2.7.3 PF 411 = 0.3


2.8.1 The Axial Flux Difference (AFD) Acceptable Operation Limits are provided in Figure 5.

2.9 Boron Concentration {Specification 3.9 .1)


This concentration bounds the condition ofkerr!S; 0.95 (all rods in less the most reactive rod) and subcriticality (Bl! rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion. The boron concentration includes credit for Samarium.

PageS of13


Tablet F Q(Z) PENALTY FACTOR

Cycle Burnup F Q(Z) Penalty Factor (MWD/MTU) Cycle Burnup F Q(Z) Penalty Factor (MWDIMTU)

0 1.0591 6241 1.0259 ISO 1.0591 6458 1.0265 368 1.0628 6893 1.0241 S8S 1.0652 7111 1.0243 803 1.0661 7328 1.0244 1020 1.0640 7546 1.0243 1455 1.0495 7763 1.0241 1890 1.0338 8199 1.0236 2325 1.0200 8416 1.0233 5806 1.0200 8851 1.0200

Notes:

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


3. For all cycle bumups outside the range of the table, a penalty factor of 1.020 shall be used.

Page6ofl3


Table 2 RAOCW(Z)

Axial Elevation 150 4000 12000 20000 Point (feet) MWD/MTU MWD/MTU MWDIMTU MWD/MTU

1-5 11.071- 11.267 1.0000 1.0000 1.0000 1.0000 6 11.(166 1.31.'11 1.3680 1.2203 1.246!1 7 111.865 1.3%71 1.35114 1.2l30 1.2436 8 10.664 1.3071 1.3490 1.2ll6 1.2326 9 10.462 1.2854 1.3357 1.2229 1.2175 10 10.261 1.2690 l.l157 1.2226 1.2050 11 10.060 1.2510 1.2939 l.ll32 1.1937 12 9.859 1.2304 1.27118 1.2266 1.1974 13 9.658 1.2306 1.2469 1.2197 1.1013 14 9.456 UZ73 • 1.23011 1.2111 1.2046 15 9.255 1.2152 1.2187 1.2096 1.2073 16 9.054 1.2113 1.200 1.2054 1.2108 17 8.853 1.2197 1.1924 1.1938 1.21U 18 8.652 1.2101 1.1927 1.1869 1.2104 19 8.450 l.ll38 1.1!165 1.1904 1.2138 10 8.249 1.ll39 1.1984 1.1944 1.ll37 21 &048 l.ll87 1.1986 1.2107 1.2395 n 7.847 1.2199 l.I!IQ 1.2096 1.2518 l3 7.646 1.2188 1.1921 1.2136 1.2613 24 7.444 1.2156 1.1867 1.2160 1.2712 l5 7.243 1.2196 1.1789 1.2149 1.2758 l6 7.00 1.2114 1.1695 1.2111 1.2768 17 6.841 l.l018 1.1590 1.2056 1.2757 18 6.640 1.1908 1.1506 1.1989 1.2718 19 6.438 1.1783 1.1417 1.1902 1.2700 30 6.237 1.1655 1.1326 1.1810 1.2654 31 6,036 1.1548 1.1157 1.1711 1.2595 32 5.835 1.1466 1.1109 1.1605 1.2521 33 5.634 1.1383 1.1165 1.1607 1.2430 34 5.431 1.1349 1.1188 1.1617 1.2376 35 .'1.231 1.1361 1.1290 1.1700 1.2380 36 5.030 1.1418 1.1378 1.1765 1.2<409 37 4.819 1.146!1 1.1464 1.1821 1.2415 38 4.618 1.1517 1.1544 1.1865 1.2401 39 4.416 1.1569 1.1619 1.1898 1.2367 40 4.215 1.1610 1.1685 1.1917 1.2315 41 4.1114 1.11542 1.1744 1.1929 1.2149 42 3.813 1.1673 1.1795 1.1935 1.2154 43 3.621 1.1729 1.1835 1.1!130 1.2101 44 3.420 1.1789 1.1882 1.1915 1.1906 45 3.219 1.1835 1.1925 1.1899 1.1771 46 3.018 1.1873 1.2046 1.1930 1.1743 tf7 1.817 1.1934 1.2243 1.2051 1.1815 48 1.616 1.2079 1.21(71 1.1186 1.1945 49 1.414 1.2243 1.2711 1.2317 1.2062 50 1.113 1.2404 1.2968 1.2449 1.2181 51 1.011 1.2567 l.l215 1.2571 1.2282 52 1.811 1.2718 1.3459 1.2687 1.2378 53 1.610 1.2883 1.3691 1.2801 1.2480 54 1.4111 1.3032 l.l9ll 1.2913 1.25811 55 1.207 1.3175 1.4117 1.3010 1.2697 56 1.006 1.3310 1.4310 l.ll23 1.2811

57-61 0.805 - 0.000 1.0000 1.0000 1.0000 1.0000

Top and Bottom 5 Points EliCiuded per Technical Specification B3.2.1.

These W(Z) values are consistent with Figure 5, and are valid over the HFP T avg temperature range from 583.8 to 586.8°F.

•• ··- ' iU. .. ' I -· ·-r ........ . ~ ,. ...

Page 7 ofl3

.. -· .... ... ... ..... , •'


FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND

VENTED AND AT LEAST ONE REACfOR COOLANT PUMP RUNNING)

5.0 r-~~ --~~~,~----~~~~,~~~,--., ~~~-~ .. ~,-~. ~~+~~~.J~ ~rl-~1-~~~~~~:~-~~r+~ -~~~ l ! I ' I ; I I I I I I II j 4.0 ~1-;-+-+-r-r,_~+-r-~~~-+-+-r-r,_+-+-~!~-;

I !ACCEPTABLE OPERATING REGION J I I i I I - +--+-+---"11 I I i I ; I ___J_J._ - -

r-+-f-1. ,,--- ' : -t-t I I ! I I -~ i 1 I 1 I i 1 j I 1 c 500 ' l3 .lo> _,.. ;3.0 ~~-4-+-+-r~~~,-+-r~~~+-+-~,~1 ~4-+-~~-r~ .... I I [ I /"I ~ ,_J I I I - I LREQUIRED SHUTDOWN MARGIN //

~ ' ~ I ! I Y" -t---

12.o t-~J-~I' ,_~: ~I-L~(1~-oJ~,~~~·~5~)~~~'~~· ~'-~' I I i I I i....... I I I I

i I I I ' . 0 ! I ' ' I D) r-J I I __I _ _ 17t/_!rl ~' ~~~· l:;;_i ,,~1~1 ~I ~I 1-;

t--1--+-+-+-+--+--+-:--+--+-... ,v hUNAccEPTABLE oPERATING REGION 1 I I I I

I I 95) I 1. 0) I i I I I 1.0 ~~-+-+-+-r~~+-+-~~-4-+-+~~~4-+-~~-4 ! ! I I i I ! I

t , J I _ ~. , . ·-t-.... 1-....... ,-r-1 -+ -U. ·- -: ~ -~-~-; -+-t

I I I I l : I I I i : I I I 1 ; i 0.0 ~--_._.~~~~._._~~_.~_.~~~~._~~~ 0 500 1000 1500 2000 2500

RCS BORON CONCEN'l'RA'l'ION (ppm)

Page 8 of13


FIGUREl REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT

APPLICABLE)

5.0 ~~~--~~~~~~~--~~~~~~~~~~ I I 1 1 ~ I I 1

c2lsoc , •. sO) V J---+--+--+-1 - . - -f -++·-1---+-u _ _j__ f- -4--+--'~---+---4 v v

I ! VI' I I I I I I .,V I

4 . o J--t---1--+-1 --i--+-+,-• +-+ 1-1-+----f-+-+ 11-+--+--~--+--111----h ~ ;c+-+--+T--+-. +-1

1 , ,ACCEPTABLE OPERATING REGION VV j

i J -- -!. J _ _j___L_ --l---h.l~4--l--1----+---L-~--4i--4-.-l ! I I I I ! I I I j' I

:ii , ' I I I ' I I ~v I I ) I I 1 I ~v I 1 i I ~3.0 ~~-+~~4-+-~~-+-+-b~4-+-~~-+-+-4-~~ a llru:OUIRED SHUTDOWN MARGIN! 1v(l~SI • 1.JS) ' 1~ l a I l ; __ _j -7:-,- ~ - -- -L 1. t -+--~ __L!_.J_, -1

! 2. o t--+1---+--+--1 +-+-+--+-1 +-,If/~: -f-.j! i'---+-1 --+--+--~1

I -+-I -+--+-+-+-1 ~~ B l I I / l l i I I ~ I I Jl'i !UNACCEPTABLE OPERATING REGION!

I v I l T

I I ..-V I I I I I I I 1. 0 ~~-+[~~4-+-+-~~-+~~4-+1~-~, -+~~~~

(4~0, l.bO) I I

I I --~---~-' J_ ~~ -1--j. I H-LI I I I t ~--+--4--1-, --1-1-+1--t

I l ; I I I I i ; I I I I I ~ I I 0 . 0 ~~~_.~~~._~~_.~~~~._~~~~~~ 0 500 1000 1500 2000 2500

RCS BORON CONCENTRATION (ppm)

Page9 of13

".: • •• .:•::·.~~-··'' ..... ..;;---· .., ;•' 41~ .... ~ ... -·":~" ;••••• .. ll. "' .. 1~ I - .... ,_ ...... ' -..~. -..

-~·---'--"---'--' • .. lt• .,. a•

,•"! : ' .


FIGURE3 ROD BANK INSERTION LIMITS VERSUS% OF RATED mERMAL POWER

220 ~

" " " ~

200

-liRamr B ~

~ ~ 180

II " ! 160 ~ ~ ., ll , ~ll) If Ill IJII'

~ ; 140 II

1120

Ll:&aNK C 1..1 1..11 1..1!

~

" It

~ " II v " ~ 100 1-f

It: I ~

2 - I I

a 80 JJDo~U~~n D ~

IJ § 60 ~ ~ tl

II Ill" il"' " 40 1' I II' '' " l

_l

20 -, t a~ ~ 12i !0 j_

~ j_ 0 l_

0 10 20 30 40 50 60 70 80 90 POWER (% 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.

~~~~

100

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 II 5 steps.

Page 10 of13

CORE OPERATING LIMITS REPORT. YEGP UNIT 2 CYCLE 18 JUNE201S

FIGURE4 K(Z)- NORMALIZED F Q(Z) AS A FUNCTION OF CORE HEIGHT

1.4 i i ~ 1

I I I -- - -. - ·-- ! ,. ··r--I

1 !

I I • l i ' I !

1.2

- - ---·- l - t -I ' I I l I I I I I '

~ I I I

' ' . -- ! - - -- - ' - - --\ ~

I I J'Q = 2.5 I . t

l I I I CORE L -1--. - -- --HT. K(Z) I I

-N ; 0.4

I ---- ---- I I

l I 0.00 1.00 I

6.00 1.00 J

12.0 .925 i I ._ - I . - r -

l I

I I I ' I I ........ ----1 . ·- --.- ·- -

I

I • I I I

! I

' 0.2

I . - -·- - . - ' -. -,-. I ! I I ! I I ! 0.0

0 2 4 6 8 10 12 CORE HEIGHT (feet)

Page 11 ofl3

" • r • ... ~ • • ...... • .~. 111

l ":1 ~. •

r l ~ I • - o .I ,, ' I ~ • I l • 1 t ,. .. ," • ol ~

....... r ~··~ ~,.. '"' ..... ··t ~ ... • ·1:' ....... --·· ·-~· ..... --~ ~ ._ ..... , .•••• ' ••""""';-' • • .,., ... • • ~ :···~. ... I .. "• ltl I 4 tf ---~--

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 18 JPNE2015

FIGURES AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF% RATED THERMAL POWER

FORRAOC

-~ I 0

Cli

" I ,; ] ~ IH 0

iiP -!

120

110

100

90

80

70

60

50

40

30

20

I I I I I I l -L I I ---r·· +-- t --- - -- t - -- ... I -

r ' I ! I I

.L I I -I ' • - - t {-15, 100) I ' - •I (+10, 10ol 1 T r- ..

I I i I I __ I I f I ' T:- l-- I J I I ---- ·- -- . - I - I l tm ~d.:..- I ' ,. ~. · ·-~

-I I I /_ ! I \ -- I

l '--- t - ~-- l : - . - -l -i !

--11 I I t\ I I I J --. -1- !-- -- -~r- -r >--- ' I . .I CCJ!Ip.t'.l l ' I

I

·~ i I ' i

- ! - -- t - -;-- - f- \ ~ - c- - ! • 1

- --I ;

' t -V-t-- I _ __! __ I \ I f

-~- --' - t j_ - -· I J t

1 I ' I ' ' I

i ' I I I I \· --L <-3o, SO )_I ~_,\ ' 1 <+26, SO)L_ ·I-- ---~- ~

l I

1 . I j I _l_ l . . __ J_ -- 1-j I

! -· ! I r --- ! -T ' ' I

' I

I I ' l I I I I -- t-- - I - -- - r-- - - ·- • _j__ I I I L I I

l I

' ·-' - -- - -~ -

10 I I

' j l I I

1 r ! I I --4 ' -- - - I - r--- - . -- - -i I I I I 0 -so -40 -30 -20 -10 0 10 20 30 40 50

AXIAL FLUX DIJ!'!'ERENCE (percent AI)

Page 12 ofl3

CORE OPERATING LIMITS REPQRT. VEGP UNIT 2 CYCLE 18

FIGURE6 Predicted HFP 300 ppm MTC vs Cycle Burnup

r; 0

l i

-27.5

·s -28.o ·rf

i • B Ill 1 -28.5 E1

B

J

~

-29.0 17000

....... ~ .......,

' .......,

' "' ' ' ~ ' ~ '~ ~

"

18000 19000 20000 Cycle Burnup (MND/MTU)

~

Cycle Burnup Moderator Temperature (MWD/MTUl Coefficient (pcmrF)

17000 -27.63 18000 -27.90 19000 -28.16 20000 -28.42 21000 -28.72

JUNE201S

I' '-

21000

Page 13 of13

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