NL-10-1486, Cycle 23 Revision 1 Core Operating Limits Report

From kanterella
Jump to navigation Jump to search
Cycle 23 Revision 1 Core Operating Limits Report
ML102290225
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 08/17/2010
From: Marino P
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-10-1486
Download: ML102290225 (17)
v • d • e


Text

Paula M. Marino Southern Nuclear Vice President Operating Company, Inc Engineering 40 Inverness Center Parkway Birmingham, Alabama 35242 Tel 205.992.7707 Fax 205.992.6165 pmmarino@southernco.com SOUTHERN'\'

August 17, 2010 COMPANY Docket Nos.: 50-348 NL-10-1486 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant-Unit 1 Cycle 23 Revision 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 1 Cycle 23 Revision 1.

This letter contains no NRC commitments. If there are any questions, please contact Mr. N. J. Stringfellow at 205-992-7037.

Sincerely, Paula M. Marino Vice President Engineering PMM/PAH/lac

Enclosure:

Core Operating limits Report FNP Unit 1 Cycle 23 Revision 1

U. S. Nuclear Regulatory Commission Log: NL-10-1486 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. M. J. Ajluni, Nuclear Licensing Director 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 Mr. P. Boyle, NRR Project Manager Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer State of Georg ia Mr. C. Clark, Commissioner-Department of Natural Resources

Joseph M. Farley Nuclear Plant - Unit 1 Cycle 23 Core Operating Limits Report Enclosure Core Operating Limits Report Unit 1 Cycle 23, Revision 1

Joseph M. Farley Nuclear Plant - Unit 1 Cycle 23 Core Operating Limits Report Enclosure Core Operating Limits Report Unit 1 Cycle 23, Revision 1

SOUTHERN COMPANY A.

Energy to Serve lOur WOrM'"

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 .. Cycle 23 Revision 1

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION I JULY 2010 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 23, Revision 1 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~ I)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.l.l 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 dT (OTdT) and Overpower dT (OPdT) 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 OPERATfNG LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULy 2010 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 MARGfN - MODES 1 and 2 (with km> 1.0) (Technical Requirement 13.Ll) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent tJdk.

2.2 SHUTDOWN MARGIN - MODES 2 (with ~< 1.0),3,4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (~ff < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1. 77 percent tJdk.

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

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 10-4 AkJkjoF for power levels up to 70 percent RTP with a linear ramp to O.1klkl°F at 100 percent RTP.

The EOLIAROIRTP-MTC shall be less negative than -4.3 x 10-4 Llk/kJop; 2.3.2 The MTC Surveillance limits are:

The 300 ppmlAROIRTP-MTC should be less negative than or equal to

-3.65 x 10-4 Llk/kJoF.

The 100 ppmlAROIRTP-MTC should be less negative than -4.0 x 1O'48k/k!°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 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 of12

CORE OPERATING LIMITS REPORT, FNP UN1T I CYCLE 23, REVISION I JULY 2010 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 - FiZ) (Specification 3.2.1)

F RTP 2.6.1 FQ(Z) '5, _Q-

  • K(Z) for P > 0.5 P

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

RATED THERMAL POWER 2.6.2 F;rp =2.50 2.6.3 K(Z) is provided in Figure 2.

2.6.4 forP > 0.5 pRTP *K(Z)

F (Z) < - Q " " - - - - forP ~ 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 UNlT I CYCLE 23, REVISION 1 JULy 2010 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F~ (Specification 3.2.2)

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

RATED THERMAL POWER 2.7.2 F!::, 1.70 2.7.3 PFMf 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 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 .6T (OT.6 T) and Overpower .6T (OP.6T)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature.6T (OT.6T) and Overpower

.6T (OP.6T) 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 ;5; 580.3°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 ofk.,ff$ 0.95 (all rods in less the most reactive rod) and subcriticality (.!ill 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 1 CYCLE 23, REVISION 1 JULY 2010 Table 1 FQ(Z) Penalty Factor I Cycle FQ(Z)

Burnup Penalty (MWDIMTlJ) Factor 30 1.027 150 1.027 354 1.033 558 1.036 763 1.037 967 1.034 1171 1.029 1375 1.023 1580 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 of31 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 intennediate 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 1 CYCLE 23, REVISION 1 JULY 2010 Table 2 Reactor Trip System Instrumentation - Overtemperature aT (OTaT)

Setpoint Parameter Values p' = 2235 psig K1=1.17 K2 = 0.017/oF K3 = 0.000825/psi "1 ~ 30 sec 't2::> 4 sec "4= 0 sec "5::> 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 Page 6of12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULY 2010 Table 3 Reactor Trip System Instrumentation - Overpower.6.T (OP.6.T)

Setpoint Parameter Values 1<4= 1,10 Ks = 0.02/°F for increasing Tavg K6 = 0.00109/°F when T > Til

=

Ks O/oF for decreasing Tavg ~ = O/oF when T ::; Til

.3<!: 10 sec

.4= 0 sec

.s::; 6 sec

.6:5: 6 sec f2(.6.I} = 0% RTP for all .6.1 Page 7 ofl2

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULY 2010 Table 4 RAOCW(Z)

Axial Point ElevatioD (feell lS0MWDfMTU lllOO MWDIMT 1111100 MWDIMTU 18000 MWDIMTU

  • Il.OO I 1 1.0000 1.0000 1.0000 1.0000 2 11.80 1.00&0 1.0000 1.0000 1.0000 I 3 I 11.60 1.0000 1.0000 1.0000 1.0000 4 11.40 1.0000 1.0000 1.0000 1.0000
11.20 1.0000 1.0000 1.0000 1.0000 6 1I.00 1.2003 1.2659 1.2557 1.2569 7 10.80 1.1959 1.2591 1.2533 1.2430 I 8 10.60 1.1889 1.2497 1.2511 1.2290 9 10AO 1.1819 1.2395 1.2489 1.2243 10 10.10 1.1741 1.2283 1.2416 1.2175 II 10.00 1.1652 1.Z164 1.2295 1.n03 12 9.80 1.1640 1.2038 1.Z274 1.2033 13 9.60 1.1657 1.1930  !.ZIS7 1.2070 14 9.40 1.1641 U87l 1.2264 1.2165 I IS 9.20 1.1611 1.1781 1.2227 1.l238 16 9.00 1.1559 1.1688 1.2229 1.2331 17 8.80 1.1550 1.1709 1.2331 1.2452 18 8.60 1.1624 1.1812 1.1471 1.2642 19 8.40 1.1741 1.1907 1.l593 1.2854 20 8.20 1.1824 1.1976 1.2680 1.3055 21 8.00 U885 1.2020 1.2736 1.3224 22 7.S0 1.1925 1.2041 1.2763 1.3354 23 7.60 1.1942 1.2040 1.2761 1.3448 24 7.40 1.1942 1.2019 1.2731 1.3504 25 7.20 1.1934 1.1979 1.2676 1.3526 26 7.00 1.1911 1.1921 1.2598 1.3514 27 6.80 1.1871 1.1849 1,2498 1.3470 28 6.60 1.1817 1.1763 1,2380 1.3397 29 6.40 1.1751 1,1665 1.2244 1.3296 30 6.20 1.1674 1.1555 1.2094 1.3169 31 6.00 1.1588 1,1443 1.1955 1.3017 32 5.80 1.1487 1.1331 1.1833 1.2847 33 5.60 1.1396 1.1246 1.1707 1.2641 34 5.40 1.1430 1.1320 1.1609 1.2434 35 5.20 1.1508 1.1384 1.1565 1.2344 36 5.00 1.1579 1.1439 1.1547 1.2267 37 4.80 1.1644 1.1491 1.1526 1.2190 38 4.60 1.1701 1.1533 1.1491 1.2116 39 4.40 1.1748 1.1567 1.1446 1.2017 40 4.20 1.1786 1.1592 1.1391 1.1900 41 4.00 1.1814 1.1608 1.1325 1.1765 42 I 3.80 1.1833 1.1612 1.1248 1,1613 43 3.60 1.1840 1.1615 1.1170 1.1448 44 3.40 1.1843 1,1629 1.1111 1.1273 45 ;UO 1.1897 1.1651 1.1068 1.1104

! 46 3.00 1.1991 1.1755 1.1032 1.1053 47 2.80 1.2149 1.1925 1.1036 1.1148 48 2.60 l.l368  !.lID8 1.1090 1.12110 !

49 2.40 1.2602 1.2288 I.U59 1.1404 50 2.20 1.2833 1.2466 1.1229 1.1529 51 2.00 1.3059 1.2640 1.1307 1.1653 52 1.80 1.3278 1.2809 1.1391 1,1777 53 l.60 1.3489 1.2971 1.1476 t.1902 i S4 1.40 1.3688 1.3123 1.1561 l.Z026 55 1.20 1.3874 1.3265 1.1646 1.2150

~

1.1726 56 1.00 1.4042 1.3392 1.2269 57 0.80 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1.0000 1.0000

  • 59 0.40 1.0000 1.0000 1.0000 1.0000
    • 60 61 0.20 a.OB 1.0000 1.0000 I.1lO0a 1.0000 1.0000 1.0000 1.0000 1.0000

Page 8 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULY 2010 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn 225 to 231 steps, inclusive 225 200 3m I I I

(.552,225)

I I

m tum " (1,187)_

1150 e

'g

.r:.

~

175

- "_ Banke

  • 3: ~

~

125 I , I I c I I

- (0, 114) 111'

~(/l 100 II

~ I I

~

.>t!

~

c:

'g 75 Bank D m

~

50

~

~ W I I I I 25 m:tttm

~

(.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 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 9 0[12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULy 2010 Figure 2 K(Z) - Normalized F Q(Z) as a Function of Core Height 1.2 1

1 0

(J CIS u..

C) 0.8 c:

CIS (I)

Il.

't7 (I) 0.6

.!:f Core Height {ft.} K(Z)

Cii 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)

Page 10 ofl2

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULY 2010 Figure 3 Axial F1ux Difference Limits as a Function of Rated Thermal Power for RAOe 120 110

(-10,100) (+9,100) 100 I

90 r- UNACCEPTABLE OPERATION I ~  !

UNACCEPTABLE OPERATION r-

~

w 3: 80 I \

0 11.

..J

!l 70 V ACCEPTABLE ~

OPERATION

/

0::

w

x::

1-. 60 0

t:!

0:::

'0 50 J 1\

(+24,50)

,e (-28,50)

L

... 40

0 11.

30 20 10 o

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

Page 11 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 23, REVISION 1 JULY 2010 Figure 4 Reactor Core Safety Limits 680 1<>-' r-...

II UNACCEPTABLE OPERATION II 660 0

r--... .........

10.. I'- , ,

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

......... , ~

640 .........

r-...

~ r-...

""" , r--....

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

r....... 1"'0 I'-.... , r--.. r-...r-.,

1\ ~2425psig Ix... , I'-.... r....... """ ......... ......

\ 2235 pslg j'-.... I'-.... r....... ~ ....... \ -&-1985 psig r.......

r.......

..... , ~ 1\

-X-1825 psig

""" r--... j'-.... \~

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

600 , r--.... " """ .........

I ACCEPTABLE I

'" , , r-..... "

I OPERATION I t'-,

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

Page 12 of 12

Retrieved from "https://kanterella.com/w/index.php?title=NL-10-1486,_Cycle_23_Revision_1_Core_Operating_Limits_Report&oldid=2556269"