NL-11-2137, Cycle 22 Version 1 Core Operating Limits Report

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Cycle 22 Version 1 Core Operating Limits Report
ML113070612
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 11/03/2011
From: Ajluni M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-11-2137
Download: ML113070612 (16)
v • d • e


Text

Mark J. Ajluni. P.E. Southern Nuclear Nuclear Licensing Director Operating Company. Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205992.7885 SOUTHERN November 3,2011 COMPANY Docket Nos.: 50-364 NL-11-2137 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 22 Version 1 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 - Unit 2 Cycle 22 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Jack Stringfellow at (205) 992-7037 ,

Sincerely,

~~Uf--

M. J. Ajluni Nuclear Licensing Director MJAlRMJllac

Enclosure:

Core Operating Limits Report FNP Unit 2 Cycle 22, Version 1

U. S. Nuclear Regulatory Commission NL-11-2137 Page 2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Ms. P. M. Marino, Vice President - Engineering Mr. W . R. May, Principal Engineer - Engineering Systems Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. V. Sreenivas, NRR Project Manager - Farley Mr. E. L. Crowe , Senior Resident Inspector - Farley

Joseph M. Farley Nuclear Plant - Unit 2 Cycle 22 Version 1 Core Operating Limits Report Enclosure Core Operating Limit.s Report for FNP Unit 2 Cycle 22, Version 1

SOUTHERN"'\'

COMPANY Energy t.o Serve Your World" Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 22 Version 1

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 22 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical Requirement affected by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 (with kcfT~ 1)

The Technical Specifications affected by this report are listed below:

2.1. 1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with 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 ChalUlnel 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 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 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 kerr:~ 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ~kJk .

2.2 SHUTDOWN MARGIN - MODES 2 (with kerr: < 1.0), 3, 4 and 5 (Specification 3.1. 1) 2.2.1 Modes 2 (lccrr < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ~kJk.

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

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. ~k1kJoF for power 4

levels up to 70 percent RTP with a linear ramp to 0 ~kJk/oF at 100 percent RTP.

The EOLIARO/RTP-MTC shall be less negative than -4 .3 x lOA ~kJkJ OF .

2.3.2 The MTC Surveillance limits are:

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

-3.65 x 10. ~kJkJOF.

4 The 100 ppmlAROIRTP-MTC should be less negative than -4.0 x 10- ~k1kJOF.

4 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 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 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 1.

2.6 Heat Flux Hot ChalU1el Factor - FQ(Z) (Specification 3.2 .1)

RTP F

2.6.1 FQ(Z)~-Q-*K(Z) for P > 0.5 P

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

RATED THERMAL POWER P

2.6.2 Ft =2.50 2.6.3 K(Z) is provided in Figure 2.

RTP F *K(Z) 2.6.4 F (Z) < -Q"------- for P > 0.5 Q - P*W(Z)

F RTP

  • K(Z)

F (Z) < --=-Q- - - for P ~ 0.5 Q - 0.5*W(Z) 2.6.5 W(Z) values are provided in Table 4.

2.6.6 The FQ(Z) penalty factors are provided in Table 1.

Page 3 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F~, (Specification 3.2.2) 2.7.1 FM N < F RTP I- 6H

  • ( 1+ PFMI * (1 - p))

where: P =- -THERMAL

- - - -POWER---

RA TED THERMAL POWER 2.7.2 F::/ = l.70 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 concentra tion shall be greater than or equal to 2000 ppm. J 2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES I and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.

2. 11 Reactor Trip System Instrumentation Overtemperature L'lT (OTL'l T) and Overpower L'l T (OP L'l T)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature L'l T (OTL'l T) and Overpower L'l T (OPL'lT) setpoint parameter values for TS 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 S; 580.3°F; and
c. The minimum RCS total flow rate shall be ~ 263,400 GPM when using the precision heat balance method and ~ 264,200 GPM when using the elbow tap method.

This concentration bounds the condition of kerr S; 0.95 (all rods in less the most reactive rod) and subcriticality (~ rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.

Page 4 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Table 1 FQ(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWD/MTU) Factor 4846 1.0206 5050 1.0238 5254 1.0263 5458 1.0274 5663 1.0248 5867 1.0225 Notes:

1. The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ(Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0 .2) starting from the burnup at which the FQ(Z) was determined.
2. Linear interpolation is adequate for intermediate cycle bumups.
3. For all cycle bumups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 5 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Values pi = 2235 psig 1<3 = 0.000825/psi

'1 ~ 30 sec '2:<:; 4 sec

'4 = 0 sec '5:<:; 6 sec '6':; 6 sec h(llI) = -2.48 {23 + (qt - qb)} when (qt - qb) ~ -23% RTP 0% of RTP when -23% RTP < (qt -gb) :<:; 15% RTP 2.05 {(qt - qb) -IS} when (qt - qb) > 15% RTP Page 6 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Table 3 Reactor Trip System Instrumentation - Overpower ~T (OP~T)

Setpoint Parameter Values "K4 = 1.10 Ks = O.02;oF for increasing Tavg K6 = 0.00109;oF when T > T" Ks = O;oF for decreasing Tavg K6 = O;oF when T ~ Til

'3~ 10 sec

'4 = 0 sec

'5~ 6 sec

'6~ 6 sec f2(~I) = 0% RTP for all ~I Page 7 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Table 4 RAOCW(Z)

Axial Point Elevation (feet) 150 MWO/ MTU 3000 MWO/MTU 10000 MWO/MTU 14000 MWO/MTU 18000 MWO/MT U

    • 1 2

12.00 11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

    • 3 4

11.60 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • 5 6

11.20 11.00 1.0000 l.J241 1.0000 1.1469 1.0000 1.2545 1.0000 1.2405 1.0000 1.2483 7 10.80 1.1198 1.1457 1.2443 1.2366 1.2434 8 10.60 1.1127 1.1416 1.2325 1.2299 1.2345 9 10.40 1.1 070 1.1376 1.2204 1.2233 1.2276 10 10.20 1.1039 1.1335 1.2143 1.2169 1.21 95 11 10.00 1.0999 1.1360 1.2190 1.2142 1.2113 12 9.80 1.1028 1.1386 1.2243 1.2118 1.2011 13 9.60 1.1081 1.1376 1.2285 1.2072 1.2000 14 9.40 1.1107 1.1364 1.2321 1.2044 1.2100 15 9.20 1.1133 1.1372 1.2327 1.2092 1.2198 16 9.00 1.1 130 1.1342 1.2365 1.2162 1.2347 17 8.80 1.1171 1.1373 1.2443 1.2212 1.2457 18 8.60 1.1290 1.1476 1.2567 1.2322 1.2586 19 8.40 1.1422 1.1586 1.2710 1.2508 1.2800 20 8.20 1.1 527 1.1670 1.2812 \.2646 1.3015 21 8.00 1.1611 1.1732 1.2881 1.2754 1.3193 22 7.80 1.1676 1.1774 1.2918 1.2833 1.3332 23 7.60 1.1719 1.1794 1.2924 1.2880 1.3433 24 7.40 1.1745 1.1798 1.2900 1.2897 1.3497 25 7.20 1.1768 1.1797 1.2847 1.2886 \.3525 26 7.00 1.1773 ].1780 1.2769 1.2863 \.3519 27 6.80 1.1763 1.1747 1.2668 1.2820 1.3481 28 6.60 1.1738 1.1700 1.2546 1.2753 1.3413 29 6.40 1.1702 1.1642 1.2405 1.2665 1.3318 30 6.20 1.1654 1.1573 1.2249 1.2557 1.3198 31 6.00 1.1 594 1.1492 1.2073 1.2434 1.3052 32 5.80 1.1 561 1.1423 1.1910 1.2283 1.2889 33 5.60 1.1 576 1.1434 1.1773 1.2148 1.2688 34 5.40 1.1698 1.1 535 1.1 679 1.2084 1.2490 35 5.20 1.1802 1.1619 1.1667 1.2063 1.2434 36 5.00 1.1897 1.1694 1.1660 1.2052 1.2408 37 4.80 1.1 986 1.1764 1.1642 1.2030 1.2363 38 4.60 1.2065 1.1824 1.1614 1.1990 1.2297 39 4.40 1.2133 1.1874 1.1575 1.1934 1.2211 40 4.20 1.2191 1.1914 1.1523 1.1862 1.2105 41 4.00 1.2231 1.1945 1.1461 1.1 775 1.1980 42 3.80 1.2286 1.1962 1.1 388 1.1671 1.1830 43 3.60 1.2357 ].1972 1.1308 1.1559 1.1682 44 3.40 1.2425 1.1979 1.1219 1.1434 1.1569 45 3.20 1.2537 1.1979 1.1138 1.1287 1.1465 46 3.00 1.2642 1.2105 1.1186 1.1280 1.1436 47 2.80 1.2837 1.2327 1.1297 1.1386 1.1485 48 2.60 1.3130 1.2563 1.1392 1.1508 1.1647 49 2.40 1.3397 1.2796 1.1490 1.1624 1.1786 50 2.20 1.3660 1.3025 1.1586 1.1738 1.1925 51 2.00 1.3916 1.3249 1.1681 1.1851 1.2063 52 1.80 1.4162 1.3465 1.1775 1.1962 1.2201 53 1.60 ],4395 1.3672 1.1869 1.2073 1.2338 54 1.40 1.4614 1.3866 1.1 961 1.2182 1.2475 55 1.20 1.4816 1.4046 1.205 I 1.2290 1.2611 56 1.00 1.4998 1.4207 1.2135 1.2393 1.2742

    • 57 58 0.80 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
    • 59 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 Page 8 of 12

CORE OPERA TfNG LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 I I I I I I

(.552,225)

~

~

200 I;'

(1,187) _

175 1/

I.;' I'

~

Banke c: L

~ 150 L ~

~

"'C

~

~

§ L I.;'

li 125 l' CIl

~

c: ~

(0, 114) g ~

'iii 100 0

c.. ~ BankO c:

IV

!Xl

"'C 75 0 L a::

50 ~

~

1/

~

25 L

~ (.070,0) o I I I 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 9 of J2

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1,2 1

...0 U.

(J III 0.8 Cl C

~

III Q) a.

0.6 Q)

Core Height (ft.} K(Z)

III 0.000 1.000 E

0 6.000 . 1.000 z 12.000 1.000 N 0.4

~

Fa = 2.50 0.2 o

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

Page 100f12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 2011 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110

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

_ UNACCEPTABLE

/ \ UNACCEPTABLE 90 II OPERATION Ci" w

3: 80 OPERATION

\

0 a.

...J

~

~ 70 / ACCEPTABLE \

a::

w J:

V OPERATION 60 J 0

....w

~ 50

-0 V _\

(+24, 50)

~

(-30, 50)

L.

QI 40

~

0 a.

30 20 10 o

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

Page 11 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 22 AUGUST 201 1 Figure 4 Reactor Core Safety Limits 680 1<>"

I 1

UNACCEPTABLE OPERATION J

I i'- t.....

660 ..........

I"'-- r-.",

10... I"'-- I'-

I'-- I'--

I' I' I'-- I'- I'--

640 I' t.....

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

I'- r--...

I'- I'-- I"'--

I'- I'- ~

t.....

I'- f'.,

~

Q) I'-- I' 1\ ~2425psig

~ Ix... I'-- I"'--

r---. r--... \ -a- 2235 psig Cl Q) 620 I'- I'--

~ ........

Cl I'-- I"---.

I"- I"---.

t""- r--.. \ ~1985 psig

-X-1825 psig RI t- I'-I"--" I"'- t-..... 1\

I'-- t-.... " r---. 1 I"--"

I.......... " l"- f"-,

600 t""-

I'- I.. . . . .

.......... I' ........

I ACCEPTABLE I ..........

b-I OPERATION I ~

580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)

Pagel2ofl2

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