NL-10-0800, Cycle 21 Core Operating Limits Report

Cycle 21 Core Operating Limits Report

ML101200110
Person / Time
Site:	Farley
Issue date:	04/30/2010
From:	Ajuni M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-10-0800
Download: ML101200110 (17)

Text

Southern Nuclear Operating Company. inc.

SOUTHERN'\

April 30, 2010 COMPANY Docket Nos.: 50-348 NL-10-0800 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Unit 2 Cycle 21 Core Operating Limits Report Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) for Joseph M. Farley Nuclear Plant Unit 2 Cycle 21, 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 Manager - Nuclear Licensing MJAlSYA/phr

Enclosure:

FNP Core Operating Limits Report Unit 2 - Cycle 21, Version 1

U. S. Nuclear Regulatory Commission NL-10-0800 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Ms. P. M. Marino, Vice President - Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley

Joseph M. Farley Nuclear Plant Unit 2 Cycle 21 Core Operating Limits Report Enclosure FNP Core Operating Limits Report Unit 2 - Cycle 21, Version 1

SOUTHERN COMPANY A.

Energy to Serve Your World" Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 21 Version 1

COLR for FNP Unit 2 Cycle 21 Version 1 Page 1 of 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 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 keff~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 keff < 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 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

COLR for FNP Unit 2 Cycle 21 Version 1 Page 2 of 13 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 AND 2 (with keff >1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent L1kik.

2.2 SHUTDOWN MARGIN - MODES 2 (with !seff < 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kef! < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent L1kik.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent L1kik.

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLIARO/HZP-MTC shall be less than or equal to +0.7 x 10-4 L1kikloF for power levels up to 70 percent RTP with a linear ramp to 0 L1kik/oF at 100 percent RTP.

The EOLlARO/RTp*MTC shall be less negative than -4.3 x 10-4 L1kikloF.

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 L1kik/oF.

The 100 ppm/ARO/RTP-MTC should be less negative than

-4.0 x 10-4 L1kik/oF.

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

COLR for FNP Unit 2 Cycle 21 Version 1 Page 3 of 13 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.

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 Channel Factor - Fo(Z) (Specification 3.2.1) 2.6.1 Fo(Z) ~

• K(Z) for P > 0.5 P

F RTP Fo(Z) ~ _ 0 -

• K(Z) for P ~ 0.5 0.5 THERMAL POWER where: P RATEDTHERMALPOWER 2.6.2 F/iTP =2.50 2.6.3 K(Z) is provided in Figure 2.

2.6.4 Fo(Z) ~ F/iTP

• K(Z) for P > 0.5 P*W(Z)

F (Z) ~ F/iTP

• K(Z) for P ~ 0.5 o 0.5* W(Z) 2.6.5 W(Z) values are provided in Table 4.

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

COLR for FNP Unit 2 Cycle 21 Version 1 Page 4 of 13 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F:L (Specification 3.2.2)

RTP 2.7.1 FNllH <

- FllH * (1 + PFllH * (1- p))

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

RA TED THERMAL POWER P

2.72 F::J =1.70 2.7.3 PF"'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 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 AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1 )

2.11.1 The Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) setpoint parameter values for TS Table 3.3.1 1 are listed in COLR Tables 2 and 3.

This concentration bounds the condition of keffs 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 uncertainties and B10 depletion.

COLR for FNP Unit 2 Cycle 21 Version 1 Page 5 of 13 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 ~ 263,400 GPM when using the precision heat balance method and ~ 264,200 GPM when using the elbow tap method.

COLR for FNP Unit 2 Cycle 21 Version 1 Page 6 of 13 Table 1 Fa(Z) Penalty Factor Cycle FQ(Z)

Burnup Penalty (MWD/MTU) Factor 5052 1.0200 5256 1.0224 5461 1.0242 5665 1.0230 5869 1.0248 6073 1.0227 6278 1.0203 6482 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 burnup at which the Fo(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.

COLR for FNP Unit 2 Cycle 21 Version 1 Page 7 of 13 Table 2 Reactor Trip System Instrumentation ~ Overtemperature AT (OTAT)

Setpoint Parameter Values P' = 2235 psig K1 = 1.17 K3 =0.000825/psi 1:1 2:: 30 sec 1:2 S 4 sec 1:4= 0 sec 1:5 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 {(% qb) 15} when (% qb) > 15% RTP

COLR for FNP Unit 2 Cycle 21 Version 1 Page 8 of 13 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values K5 = 0.02/°F for increasing Tavg K6 == 0.00109/°F when T > Til K5 =O/oF for decreasing T avg K6 == O/oF when T 5; Til 1:32: 10 sec 1:4 = 0 sec 1:5:::; 6 sec 1:65; 6 sec f2(ill) == 0% RTP for all ill

COLR for FNP Unit 2 Cycle 21 Version 1 Page 9 of 13 Table 4 RAoe W(Z)

Axial Point Elevation (feet) 150 MWD/MTU 3000 MWD/MTU 10000 MWD/MTU 18000 MWD/MTU I

2 12.00 11.80 1.0000 1.0000 1.0000 l.OOOO 1.0000 1.0000 I 1.0000 1.0000

• 3 11.60 1.0000 1.1)000 1.0000 1.0000

• 4 i 11.40 1.0000 1.0000 1.0000 1.0000 5 11.20 1.0000 1.0000 1.0000 1.0000 6 11.00 I 1.1533 1.2216 1.2775 1.2634 7 10.80 I 1.1480 1.2211 1.2136 1.2515 I 8 10.60 1.1431 1.2128 1.2670 1.2356 9 10.40 1.1425 1.2031 1.2602 1.2299 10 11).20 1.1481 1.1937 1.2523 1.2225 11 10.00 1.1526 1.1831 1.2427 1.2148 12 9.80 1.1558 1.1737 1.2414 1.2070 13 9.60 1.1571 1.1675 1.2420 1.2110 I

14 15 16 17

+/-= 9.40 9.20 9.00 8.80 1.1569 1.1554 1.1496 1.1532 1.1619 1.1542 1.1441 1.1435 1.2396 1.2355 1.2363 1.2437 1.2198 1.2262 1.2367 1.2471 18 8.60 1.1657 1.1489 1.2578 1.2666 19 8.40 1.1778 1.1598 1.2701 1.2880 20 8.20 1.1872 1.1617 1.2791 1.3088 21 8.00 1.1943 1.1734 1.2850 1.3260 22 I 7.80 1.1991 1.1772 1.2878 1.3392 23 7.60 1.2016 1.1790 1.2875 1.3481 24 7.40 1.2022 1.1791 1.2845 1.3544 25 7.20 1.2022 1.1786 1.2787 1.3566 26 7.00 1.2003 1.1767 1.2705 1.3553 21 6.80 1.1966 1.1732 1.26tH 1.3509 28 6.60 1.1915 1.1684 1.2476 1.3434 29 30 6.40 6.20 l.t849 1.1772 1.1624 1.1553 1.2334 1.2176 1.3332 1.3204 31 6.00 I.lIi86 1.1478 1.1998 1.3050 32 5.80 1.1578 1.1377 1.1853 1.2880 33 5.60 U51l 1.1332 1.1735 1.2669 34 5.40 1.1560 t.l407 1.1614 1.2464 35 5.20 1.1639 1.1473 1.1679 1.2421 36 5.00 1.1729 1.1550 1.1680 1.2395 37 4.80 1.1822 1.1629 t.l664 1.2342 I 38 4.60 1.1903 1.1696 1.1639 1.2275 39 4.40 1.1976 1.1754 1.1602 1.2192 40 4.20 1.2037 1.1803 US53 1.2090  !

41 4.00 1.2081 1.I842 1.1495 1.1968 42 3.80 1.2126 US69 1.1425 1.1831 43 3.60 1.2153 1.1890 1.1350 1.1615 44 3.40 1.2169 1.1922 1.1265 1.1532 45 3.20 1.2192 1.1971 1.1194 1.1397 46 3.00 1.2233 1.2051 1.1203 1.1362 47 2.80 1.2356 1.2167 1.1277 1.1469 48 2.60 1.2567 1.2333 1.1374 1.1593 49 2.40 1.2796 1.2550 1.1472 1.1712 50 1.3021 1.2763 1.1569 1.1832 I 51 2 2.0 . t = j 1.3242 1.2970 1.1666 1.1952 I 52 1.8 1.3457 1.3173 1.1764 1.2074 53 1.60 1.3663 1.3367 1.1861 1.2198 54 1.40 1.3866 1.3611 1.1951 1.2324 55 1.20 1.4090 1.3859 1.2051 1.2451 56 1.00 1.4295 1.4069 1.2140 1.2516

"~

• 1.0000 1.0000 1.0000 1.0000 51 58 0.60 1.0000 1.0000 1.0000 1.0000 59 0.40 1.0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1.0000 1.0000

• Top and bottom 5 axial points excluded per Technical Specification B 3.2.1.

COLR for FNP Unit 2 Cycle 21 Version 1 Page 10 of 13 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 tffi I;'

I I I

(.552,225)

I I I 200 I;'

(1,187)_

175 m Banke "2 I;' I;'

~ 150 I!! f" "C

s:. l;o

~

~ 125 I;'

!HI Em ill ,

II (I)

~

c (0, 114) 0 f""

'iii 100 0 ~

D..

.:>0:

Bank D C

I'll IX!

"C 75 I;'

0 a::

I;'

50

~

25 o

0.0 0.1

(.070,0)

I I I I 0.2 0.3 0.4 0.5 0.6 0.7 m

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.

COLR for FNP Unit 2 Cycle 21 Version 1 Page 11 of 13 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1

~

0 1:) 0.8 as LL m

c

i:

as CD Do "t:J CD 0.6

.t:! Core Height (ft.} K(Z) c; 0.000 1.000 E

~

0 6.000 1.000 z 12.000 1.000 NO.4

~

FQ = 2.50 0.2 o

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

COLR for FNP Unit 2 Cycle 21 Version 1 Page 12 of 13 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 I

110

(-12,100) (+9,100) 1 100

/

90

_ UNACCEPTABLE \ UNACCEPTABLE OPERATION

~

~

w 80 OPERATION I II \

..J

E 0:::

W J:

I 70 i

/

If ACCEPTABLE OPERATION

~ ,

Q 60 W

I

/ 1\

~

0

!e.

~

50 40

(-30, 50) (+24,50)

!II

~

0 30 20 10 o

-60 -50 -40 II

-30 -20 -10 o 10 20 30 40 LL 50 60 Axial Flux Difference (Delta I) %

COLR for FNP Unit 2 Cycle 21 Version 1 Page 13 of 13 Figure 4 Reactor Core Safety Limits 680 II UNACCEPTABLE Ir 1<>-'

r--.. ....... ti OPERATION 660 10.. lli , r--.... I it t'-. r--... r--...

I"-- I

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

640 I"--- , ~tt .......

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

r--....

r--.... r-o i"'- I'--

x.. ,

, r--.... I"--  !-.....

,, \

\

-<>- 2425 psig

....... I

, 2235 psig r--... ......... r--... ......... \ -t:r-1985 psig

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

- f\ -X-1825 psig r-......

"'\

600

,~ " .......

r--... r--.. r-... "

illI I"-- r-...

580 I

I ACCEPTABLE OPERATION I '" '" ~

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