NL-07-1998, Cycle 22 Core Operating Limits Report

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Cycle 22 Core Operating Limits Report
ML073050242
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 10/31/2007
From: George B
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-1998
Download: ML073050242 (16)
v • d • e


Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUIHERNA COMPANY October 31. 2007 Energy to Serve Your WorldS" Docket No.: 50-348 NL-07-1998 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Cycle 22 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 Farley Nuclear Plant Unit 1 Cycle 22, Rev. O.

This letter contains no NRC commitments. If there are any questions, please advise.

Since~

~ B. J. G rge

.........r -

Manager, Nuclear Licensing BJG/CHM/phr

Enclosure:

FNP Core Operating Limits Report Unit 1- Cycle 22, Rev. 0 cc: Southern Nuclear Operating Company Mr. J. 1. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; LC# 14664 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley

Joseph M. Farley Nuclear Plant - Unit 1 Cycle 22 Core Operating Limits Report Enclosure FNP Core Operating Limits Report Unit 1- Cycle 22, Rev. 0

\

SOUTHERN.A COMPANY Energy to Serve ~ur WorIJ-Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 22 Revision 0

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 1 of 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 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 kelf ~ 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 kelf < 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 1 Cycle 22 Revision 0 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 km! > 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent dklk.

2.2 SHUTDOWN MARGIN - MODES 2 (with k..f! < 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 dklk.

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

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 10-4 dklkloF for power levels up to 70 percent RTP with a linear ramp to 0 dk/kloF at 100 percent RTP.

The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 10-4

~klkloF.

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 dklkloF.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 10-4 dklkloF.

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

COLR for FNP Unit 1 Cycle 22 Revision a 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)

F. RTP 2.6.1 Fo(Z) ~ _ 0 -

  • K(Z) for P > 0.5 P

F. RTP Fo(Z) ~ _ 0 -

  • K(Z) for P ~ 0.5

0.5 where

P = THERMAL POWER RA TED THERMAL POWER 2.6.2 F;TP =2.50 2.6.3 K(Z) is provided in Figure 2.

for P > 0.5 F. (Z) ~ F;TP

  • 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 1 Cycle 22 Revision 0 Page 4 of 13 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F~ (Specification 3.2.2) where:

P = THERMAL POWER RA TED THERMAL POWER 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 L1T (OTL1T) and Overpower L1T (OPL1T) Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature L1T (OTL1T) and Overpower L1T (OPL1T) setpoint parameter values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

This concentration bounds the condition of keff $ 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 B10 depletion.

COLR for FNP Unit 1 Cycle 22 Revision 0 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 :s; 580.3 of; 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 1 Cycle 22 Revision 0 Page 6 of 13 Table 1 FQ(Z) Penalty Factor Cycle FQ(Z)

Burnup Penalty (MWD/MTU) Factor 150 1.020 558 1.031 967 1.031 1375 1.020 4439 1.020 4643 1.028 5664 1.028 6481 1.020 15875 1.020 16079 1.023 16487 1.023 16692 1.020 Notes:

1. The Penalty Factor, to be applied to Fa(Z) in accordance with SR 3.2.1.2, is the maximum factor by which Fa{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 Fa{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 1 Cycle 22 Revision 0 Page 7 of 13 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Values T' ~ 577.2 of P' =2235 psig K1 = 1.17 K2 = 0.017/ of K3 = 0.000825 / psi

't1 ~ 30 sec 't2~ 4 sec

't4 =0 sec 't5 ~ 6 sec 't6 ~ 6 sec

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

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 8 of 13 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values T" :s; 577.2 OF K.t= 1.10 Ks = 0.02 / OF for increasing Tavg K6 = 0.00109/ OF when T > T" Ks = 0 / of for decreasing Tavg K6 = 0 / OF when T :s; T"

't3 ~ 10 sec

't4 =0 sec

'ts:s; 6 sec

't6:S; 6 sec f2(LlI) = 0 % RTP for all Lli

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 9 of 13 Table 4 RAOCW(Z)

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

    • 1 2

12.00 11.80 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

  • 5 6

11.20 11.00 1.0000 1.1356 1.0000 1.2242 1.0000 1.2690 1.0000 1.2906 7 10.80 1.1338 1.2206 1.2599 1.2754 8 10.60 1.1323 1.2143 1.2480 1.2555 9 10.40 1.1305 1.2070 1.2407 1.2342 10 10.20 1.1454 1.2007 1.2318 1.2182 11 10.00 1.1507 1.1927 1.2276 1.2113 12 9.80 1.1506 1.1862 1.2235 1.2128 13 9.60 1.1493 1.1806 1.2177 1.2193 14 9.40 1.1470 1.1737 1.2113 1.2250 15 9.20 1.1423 1.1653 1.2038 1.2283 16 9.00 1.1367 1.1542 1.1945 1.2381 17 8.80 1.1381 1.1537 1.1928 1.2435 18 8.60 1.1467 1.1589 1.1981 1.2649 19 8.40 1.1567 1.1681 1.2132 1.2875 20 8.20 1.1642 1.1746 1.2242 1.3090 21 8.00 1.1696 1.1789 1.2326 1.3268 22 7.80 1.1746 1.1814 1.2385 1.3406 23 7.60 1.1779 1.1818 1.2419 1.3507 24 7.40 1.1793 1.1806 1.2428 1.3569 25 7.20 1.1790 1.1787 1.2413 1.3596 26 7.00 1.1770 1.1754 1.2391 1.3587 27 6.80 1.1736 1.1707 1.2353 1.3546 28 6.60 1.1690 1.1647 1.2293 1.3475 29 6.40 1.1631 1.1576 1.2217 1.3376 30 6.20 1.1562 1.1495 1.2124 1.3250 31 6.00 1.1489 1.1411 1.2018 1.3097 32 5.80 1.1417 1.1297 1.1893 1.2929 33 5.60 1.1432 1.1254 1.1772 1.2719 34 5.40 1.1567 1.1313 1.1706 1.2514 35 5.20 1.1681 1.1391 1.1708 1.2465 36 5.00 1.1786 1.1463 1.1705 1.2436 37 4.80 1.1886 1.1529 1.1685 1.2381 38 4.60 1.1975 1.1586 1.1656 1.2308 39 4.40 1.2055 1.1635 1.1614 1.2213 40 4.20 1.2123 1.1675 1.1565 1.2097 41 4.00 1.2180 1.1706 1.1513 1.1967 42 3.80 1.2224 1.1723 1.1445 1.1829 43 3.60 1.2255 1.1742 1.1382 1.1680 44 3.40 1.2277 1.1780 1.1346 1.1536 45 3.20 1.2285 1.1819 1.1313 1.1425 46 3.00 1.2367 1.1912 1.1260 1.1426 47 2.80 1.2493 1.2094 1.1268 1.1552 48 2.60 1.2742 1.2339 1.1367 1.1725 49 2.40 1.2987 1.2580 1.1462 1.1884 50 2.20 1.3230 1.2818 1.1558 1.2041 51 2.00 1.3468 1.3053 1.1654 1.2196 52 1.80 1.3699 1.3281 1.1749 1.2350 53 1.60 1.3921 1.3500 1.1644 1.2503 54 1.40 1.4131 1.3706 1.1937 1.2654 55 1.20 1.4327 1.3897 1.2029 1.2803 56 1.00 1.4505 1.4069 1.2114 1.2946

    • 57 58 0.80 0.60 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 61 0.00 1.0000 1.0000 1.0000 1.0000

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 10 of 13 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)

I;'

200 (1,187) _

175

~

Banke I

"C 150 ~

~

E 3: ,

It 125

~c ~

o (0, 114)

e III 100 o
0. I;'

~

BankO c

ca co

'8 75

~

~

50 25

, (.070,0)

I I I I o

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, 0 and a control bank tip-to-tip distance of 128 steps.

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 11 of 13 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1

~ca 0.8 LL C) c:::

i ca Q)

D.

"C 0.6

.~ Core Height (ft.) K(Z) iij 0.000 1.000 E

o 6.000 1.000 z I 12.000 1.000 N O.4 i"

FQ =2.50 0.2 o

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

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 12 of 13 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110

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

{

90 r-UNACCEPTABLE \ UNACCEPTABLE OPERATION -

Ci" UJ 3: 80 0

OPERATION 1/ \

~

Q.

..J c(

Ii a: 70 / ACCEPTABLE OPERATION UJ
z::

I I \

0 J UJ 60

...~

0 50 V \

~

e.....

(-30, 50) (+24,50) 0 40 Q.

30 20 10 o

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

COLR for FNP Unit 1 Cycle 22 Revision 0 Page 13 of 13 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE 1<>" OPERATION 660 r---. . . .

'" r---. r-.... ...... j"-....

10.. i"'-..

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

i"'-.. r--... 1'- . . .

640 I"""-

r--.... I'

" I' f'.

f'. ......

i"'-.. I'-..

I' N)

~

III e Ix.. I' I'

'" "" " r--... t-....

'" I' 1\

, ~2425psig

-G- 2235 psig Cl 620 i"'-.. r--..

~

III r---. j"-.... -....

Cl r--.... r--.. r--.... 1\ -tr-1985 psig

~

> . . . 1' r--.... r--.. """ 1\ -X-1825 psig

...... \

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

600 r--.... r---. r--..

f'. ......... .......

~

ACCEPTABLE .........

OPERATION ~

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

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