NL-04-2057, Cycle 20 Core Operating Limits Report

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Cycle 20 Core Operating Limits Report
ML042990392
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 10/21/2004
From: Stinson L
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-04-2057
Download: ML042990392 (14)
v • d • e


Text

L M. Stinson (Mike) Southern Nuclear Vice President Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 SOUTHERN A October 21, 2004 COMPA[

Energy to Serve Your World '

Docket No.: 50-348 NL-04-2057 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit I Cycle 20 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 20.

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

Sincerely, L. M. Stinson LMS/C-IM/sdl

Enclosure:

FNP Core Operating Limits Report Unit I - Cycle 20, August 2004 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, General Manager - Plant Farley RTYPE: CFA04.054; LC# 14162 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector- Farley

, 601

Joseph M. Farcey Nuclear Plant - Unit I Cycle 20 Core Operating Limits Report Enclosure

QQRF OPERATING LIMITS RFPQRT-OR OPRAIN L.IT FNP UNIT RE.....RT. FN UNIT .I CYCLE CYL 20 20 A.US T 2004 AIUGUS 2004......... ..........

1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT I CYCLE 20 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 I and 2 (with k~ffŽ 1)

The Technical Specifications affected by this report arc listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with k~ff< 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- FJ,(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor - Fj 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 Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration Page I of 12

CORE OPERATING LIMMS REPORT- FNP I JNIT I CYCLE 20 OR OPRTN .. P _NI . CYL 20 LIIT REPORT.......... AUGUST 2004 AUUS 2004............=._.__ ......_

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 kf_ 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

2.2 SHUTDOWN MARGIN -MODES 2 (with ff 1.0). 3,4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kff < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

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

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

The BOL/ARO/HZP-MTC shall be less than or equal to +0.7 x 104 Ak/k-/F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k-/F at 100 percent RTP.

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

2.3.2 The MTC Surveillance limits are:

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

-3.65 x 104 Ak/kl/IF.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 104 Ak/k/0 F.

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 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 COR OPERATING OPRTN LIMITS LIIT REPORT, REOT FNP FN UNIT UNI II CYCLE CYL 20 20 AUGUST AUUS 2004 2004 '--- ----

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 - Ft,(Z) (Specification 3.2.1) 2.6.1 FC(Z) S En

  • K(Z) for P > 0.5 P

FRlI' Fc,(Z) S L $*K(Z) for P S 0.5

0.5 where

= THERAML POWER RA TED THERMAL POWTER 1

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

f <(Z F(""* K(Z) 2.6.4 F,(Z) S for P > 0.5 P* WV(Z)

FI(Z)() 1

  • K(Z)fop os E (Z) S r'0.5 * (Z) for P < 0.5 2.6.5 W(Z) values are provided in Table 4.

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

Page 3 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 20 l AUGUST 2004 AUGUST 2004 CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 20 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F.,, (Specification 3.2.2) 2.7.1 F, < F,," * (I + PF * (I-P))

whcrc: P THERMAL POW1ER RATED THERMIAL POWVER 2.7.2 F2,," = 1.70 2.7.3 PFI,, =0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm.'

2.10 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 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.

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 2 2209 psig;
b. RCS average temperature < 580.30 F; and
c. The minimum RCS total flow rate shall be 2 263,400 GPM when using the precision heat balance method and 2 264,200 GPM when using the elbow tap method.

This concentration bounds the condition of ken< 0.95 (all rods in less the most reactive rod) and subcriticality (al rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B' 0 depletion.

Page 4 of 12

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 20 -AUGUST-2004 AUGUST2004 CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 20 Table 1 FQ(Z) Penalty Factor Cycle FQ(Z)

Burnup Penalty (NIVD/NITU) Factor 150 1.020 354 1.030 559 1.038 763 1.041 967 1.039 1171 1.034 1376 1.027 1580 1.020 5052 1.022 5256 1.029 5869 1.026 6482 1.020 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 burnups.
3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 5 of 12

CORE AUGUST 2004 COR OPERATING OPRTN LIMITS LIIT REPORT.

REOT

FNP

--- UNIT FN UNI ----II CYCLE CYL 20 20

AUGUST2004 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Values T' < 577.20F P'= 2235 psig Ki= 1.17 K2 = 0.017/ 0 F K3= 0.000825/psi Tl 2 30 sec T2

  • 4 sec T4 = 0 sec Ts < 6 sec T6* 6 sec fi(Al) = -2.48 f23 + (qt - qb))1 when (qt - qb) < -23% RTP 0% of RTP 'Awhen -23% RTP < (qt -qb) < 15% RTP 2.05 {(qt - qb) - 151 'Awhen (qt - qb) > 15% RTP Page 6 of 12

CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 20 AUGUST AUGUST 2004 2004 CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 20 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values T"I 577.2 0F K4 = 1.10 K5 = 0.02/ 0 F for increasing Tavg K6 = 0.00109/ 0 F when T > T" K5 = 0/0 F for decreasing Tavg K6 = 0/ 0 F when T

  • T" T32 10 sec T4 = 0 sec T5 < 6 sec T6 < 6 sec f2(Al) = 0% RTP for all Al Pagc 7 of 12

CORE OPERATING L.IMITS REtPORT. FNP IUNIT 11 CYCLE 20 ATTCdJST 20T)(04 AUGUT(Y 2004 CORP OPFRATINC, IIMIT5 RPPORT FNP UNIT CYCVP 20 Table 4 RAOC W(Z)

Axial Point Elevation (feel) 150 MWIDJIINTU 4000 5I11D/INTU 10000 MWID)NITU 18000 51MWD/ITU I 12.00 1.0000 1.0000 2.0000 I.0000 2 11.80 1.0000 1.0000 1.0000 1.0000 3 11.60 1.0000 1.0000 1.0000 1.0000 4 ItA0 1.0000 1.0000 1.0000 1.0000 S 11.20 1.0000 1.0000 1.0000 I.0000 6 11.00 1.0000 1.0000 1.0000 I.0000 7 10.80 1.0000 1.0000 1.0000 I.0000 8 10.60 I.0000 I.0000 I.0000 I.0000 9 10.40 1.0000 1.0000 1.0000 2.0000 10 10.20 1.0000 1.0000 2.0000 1.0000 2 - 10.00 1.1856 1.2470 1.2612 1.2308 12 9.80 1.1868 1.2375 1.2521 1.2269 13 9.60 1.1868 1.2269 1.2449 1.2252 14 9.40 1.1856 1.2154 1.2439 1.2231 I5 9.20 1.189 1.2031 1.2479 1.2318 16 9.00 1.1787 1.1924 1.2497 1.2521 17 8.80 1.ISI 2.1954 1.2510 1.2693 IS 8.60 1.1932 1.2066 1.2547 1.2854 19 8.40 1.2047 1.2148 1.2592 1J045 20 8.20 1.2137 1.2209 1.2613 13241 21 8.00 1.2214 1.2247 12612 13400 22 7.80 12275 1.2263 12611 13521 23 7.60 12315 1.2256 1.2628 I3607 24 7A40 12333 1.2232 1.2618 23658 25 7.20 12332 1.2198 1.2588 23673 26 7.00 1.2324 2.2150 1.2550 123657 27 6.80 12278 12086 1.2496 13609 28 6.60 1.2229 12007 12423 13532 29 6.40 1.2167 I.1918 12334 13429 30 6.20 1.2094 1.I187 12230 13301 31 6.00 1.1543 1.1479 2.1879 12891 32 5.80 2.1502 1.1356 1.1742 1.2725 33 5.60 I.I55 21.1261 1.1634 1.2523 34 5.40 1.1640 1.1288 1.1611 1.2372 35 520 1.1748 1.1356 1.1610 1.2322 36 5.00 1.2845 1.1419 1.1600 1.2284 37 4.80 1.1937 1.1473 1.1578 1.2227 38 4.60 12019 1.1521 1.1547 1.2150 39 4A.0 12090 1.1561 2.I5I5 1.2054 40 420 12150 1.1591 1.1473 1.1939 41 4.00 12198 1.1613 1.1425 1.1822 42 3.80 12234 1.1624 1.1391 1.1699 43 3.60 1.2257 1.1631 1.1350 I.I582 44 3.40 12294 1.1646 1.1315 1.1463 45 320 12412 1.1690 1.1271 1.1362 46 3.00 12559 1.1S21 1.1241 1.1329 47 2.80 1.2702 1.2026 1.1265 1.1448 48 2.60 12838 1.2257 1.13W4 1.1594 49 2.40 13010 1.2484 1.1485 1.1732 50 220 13267 12708 1.1588 1.1869 Sl 2.00 13518 1.2929 1.1693 1.2006 52 1.80 1.0000 1.0000 I.0000 I.0000 53 1.60 1.0000 I.0000 2.0000 I.0000 54 1.40 1.0000 I.0000 2.0000 1.0000 55 120 1.0000 2.0000 2.0000 2.0000 56 1.00 1.0000 1.0000 I.0000 I.0000 57 0.80 1.0000 1.0000 1.0000 I.0000 58 0.60 I.0000 I.0000 I.0000 I.0000 59 0.40 1.0000 I.0000 I.0000 I.0000 60 020 I.0000 I.0000 I.0000 I.0000 612 0.00 2.0000 1.0000 1.0000 2.0000

Figure I Rod Bank Insertion Limits versus Rated Thermal Power Page 8 of 12

CORE AUGUST AUUS 2004 COR OPERATING OPRTN LIMITS LIIT ------ REPORT, REOT FNP UNIT UNI II CYCLE FN------ CYL 20 20 2004 Fully Withdrawn - 225 to 231 steps, inclusive 225 I I I A I I I (.552,225) 200 87 oe 175 till I I VT I yl I ZI I Ba k C R: 150 Jo c

I I I I I I I I I I I V I E 125 100,

.00, I I 'd 109 I I I

I I C,

I LO I I I cn (0,114) 11 1 1 11 1 1 001 I I I 0 ++ II I I II I I I I I I I I e 100 -1 H 1 H 01 I I 0

IL Je r- I I VI-I Bank D.

M v0 75 i i i i i i i i i i i i i i Hi i i i HA Hi Hi i ! !i i i i ! i i !i i 50 I I 11 I I 1 111 I 111 11 1711 1 1 11 I 1 1 1 1 I 1 1 1 1 1 11 1 !!!  !!! I 1 11 M I I 11 111 I 111 I 171 111 11111 I 1!!! I I 111 !!! I I 11 11 11!!! 1M 25 I(01 01,11 1 I I III j (.070, °)

04-' *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 2 225 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 12

r(Mfl. OPPRATING~

CRn]. a.P- .\,

LIMITS T...

R ZEPtRT. IFP UI TT

. . (. .. . .1....

. TIN- .

I1 CYCLE rv. 20)

T....... _

AUGUST]

I T 2'0041 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1

to t-e 0.8 L-

._e a)

0) 0.6 z°DN co E

-N 0.4 IC 0.2 0

0 2 4 6 8 10 12 Core Height (feet)

Pagc I of 12

CORE OPERATING LIMITS RE.PORT. FNP UTNIT I CYCLE 20 AUGUST 2004 AUGTUST 2004 CORE OPERATING LIMITS REpORT. FNP UNIT I CYCLE 20 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110 100 90 -

. IL n(42,100)

UNACCEPTABLE t 00K 1 4 I I I I I UNACCEPTABLE 3'I 80 0

OPERATION

/ N OPERATION cz 70 I I I 7 1 I 7I i C ACCEPTABLE \ I I I I- OPERATION w

IL 0

60 CZ So I 50 I )I I (2 50 0~ 40 30 20 X11 FI 10 0

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

Page I I of I2

CORE OPERATING LIMITS REPORTS FNP UNIT I CYCLE 20 AUGUST 2004 AUGUST 2004 CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 20 Figure 4 Reactor Core Safety Limits 680 0

I - 2425 psig 0

I --0-2235 psig a 620 co I -?z1985

-X- 1825 psig psig I

560 4-0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)

Page 12 of 12

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