NL-13-2294, Cycle 26 Core Operating Limits Report Version 1

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Cycle 26 Core Operating Limits Report Version 1
ML13310A452
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 11/05/2013
From: Pierce C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-13-2294
Download: ML13310A452 (16)
v • d • e


Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Te l 205.992.7872 Fax 205 992.7601 SOUTHERN . \

November 5, 2013 COMPANY Docket Nos.: 50-348 NL-13-2294 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Cycle 26 Core Operating Limits Report Version 1 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 (FNP) - Unit 1 Cycle 26 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Sincerely, C.1i~

C.R. Pierce Regulatory Affairs Director CRP/RMJ/lac

Enclosure:

Core Operating Limits Report for FNP Unit 1 Cycle 26 Version 1

U. S. Nuclear Regulatory Commission NL-13-2294 Page 2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. Ed Miller, NRR Project Manager - Farley Mr. P. K. Niebaum, Senior Resident - Farley Mr. J. R. Sowa, Senior Resident - Farley Mr. R. E. Martin, Senior Project Manager- Farley

Joseph M. Farley Nuclear Plant - Unit 1 Cycle 26 Core Operating Limits Report Version 1 Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 26 Version 1

SOUTHERN . \

COMPANY Energy to Serve Your Wor/d*

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 26 Version 1

CORE OPERA TING LIMITS REPORT, FNP UNIT I CYCLE 26 SEPTEMBER 2013 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 26 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 and2(withk.,ffz\)

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 L\T (OTL\T) and Overpower L\T (OPL\ 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 I of 12

CORE OPERA TlNG LIMITS REPORT, FNP UNIT I CYCLE 26 SEPTEMBER 2013 2.0 OPERA TING 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 keff ~ 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 !sert:< 1.0),3,4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kerr < 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 \0.4 ~kJkJoF for power levels up to 70 percent RTP with a linear ramp to 0 ~kJkJoF at \00 percent RTP.

The EOLIARO/RTP-MTC shall be less negative than -4.3 x \0.4 ~kJkJoF.

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 I 0. ~kJkJOF.

4 The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x \0.4 ~kJkJOF.

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. I 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 I CYCLE 26 SEPTEMBER 2013 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 - FQ(Z) (Specification 3.2.1) for P > 0.5 for P ~ 0.5 THERMAL POWER where: P =---------

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

F,RTP

  • K(Z) 2.6.4 F, (Z) < - - = . Q _ - - for P > 0.5 Q - P*W(Z)

F,RTP

  • K(Z)

F (Z) < _Q:c....-_ _ 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 OPERA TING LIMITS REPORT, FNP UNIT I CYCLE 26 SEPTEMBER 2013 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. 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 t.. T (OTt.. T) and Overpower t.. T (OPt.. T)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1)

2. 11.1 The Reactor Trip System Instrumentation Overtemperature t.. T (OTt.. T) and Overpower t.. T (OPt.. T) 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:::; 580.3°F; and
c. The minimum RCS total flow rate shall be ~ 273,900 GPM when using the precision heat balance method and ~ 274,800 GPM when using the elbow tap method.

This concentration bounds the condition of kerr:::; 0.95 (all rods in less the most reactive rod) and subcriticality Uill 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 I CYCLE 26 SEPTEMBER 2013 Table 1 F Q(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWDIMTU) Factor All Bum Up Steps 1.0200 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.

Page 5 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 26 SEPTEMBER 2013 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Values T' :s; 577.2°F pi = 2235 psig K1 = 1.17 K2 = 0.017 ;OF K3 = 0.000825/psi

.1:2: 30 sec .2:S; 4 sec

.4 = 0 sec .5:S; 6 sec .6:S; 6 sec h(~I) = -2.48 {23 + (qt - qb)} when (qt - qb):S; -23% RTP 0% ofRTP when -23% RTP < (qt -qb):S; 15% RTP 2.05 {( qt - qb) - 15} when (qt - qb) > 15% RTP Page 6 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 26 SEPTEMBER 2013 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values 1<4= 1.10 Ks = 0.02rF for increasing Tavg K6 = 0.00109 rF when T > Til Ks = 0/ OF for decreasing Tavg K6 = OrF when T ~ Til

't3~ 10 sec

't4 = 0 sec

't5~ 6 sec

't6 ~ 6 sec h( ~I) = 0 % RTP for all ~I Page 7 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 26 SEPTEMBER 2013 Table 4 RAOCW(Z)

Axial Point Elevation (feet) 150 MWD/MTU 3000 MWD/MTU 10000 MWD/MTU 14000 MWDIMTU 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 1.0000 1.0000 3 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 4 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 5 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.00 1.1632 1.2116 1.2928 1.2696 1.2628 7 10.80 1.l604 1.2099 1.2746 1.2522 1.2473 8 10.60 1./539 1.2024 1.2484 1.2271 1.2253 9 10.40 1.1472 1.1946 1.2292 1.2221 1.2111 10 10.20 1.1410 1.1920 1.2149 1.2163 1.2036 11 10.00 1.1427 1.1894 1.2174 1.2080 1.1951 12 9.80 1.1477 1.1859 1.2268 1.2017 1.1923 13 9.60 1.1479 1.1828 1.2303 1.1984 1.1969 14 9.40 1.1454 1.1775 1.2341 1.1980 1.2077 15 9.20 1.1457 1.1705 1.2342 1.2067 1.2156 16 9.00 1.1427 1.1618 1.2357 1.2159 1.2247 17 8.80 1.1427 1./529 1.2420 1.2200 1.2369 18 8.60 1./530 1.1517 1.2528 1.2273 1.2533 19 8.40 1.1661 1.1637 1.2671 1.2451 1.2763 20 8.20 1.1768 1.1735 1.2782 1.2600 1.2960 21 8.00 1.1850 1.1800 1.2856 1.2712 1.3118 22 7.80 1.1910 1.1848 1.2899 1.2796 1.3242 23 7.60 1.1947 1.1873 1.2910 1.2848 1.3330 24 7.40 1.1962 1.1878 1.2891 1.2872 1.3383 25 7.20 1.1970 1.1875 1.2844 1.2865 1.3399 26 7.00 1.1963 1.J858 1.2770 1.2842 1.3394 27 6.80 1.1938 1.1825 1.2672 1.2803 1.3368 28 6.60 1.1898 1.1777 1.2553 1.2740 1.3312 29 6.40 1.1844 1.1715 1.2415 1.2655 1.3228 30 6.20 1.1778 1.1641 1.2260 1.2550 1.3119 31 6.00 1.1699 1.1564 1.2090 1.2430 1.2985 32 5.80 1.1617 1.1457 1.1906 1.2283 1.2835 33 5.60 1.1570 1.1381 1.1735 1.2137 1.2652 34 5.40 1.1583 1.1464 l.J631 1.2061 1.2448 35 5.20 1.1659 1.1546 1.1613 1.2035 1.2414 36 5.00 1.1738 1.1612 1. 1605 1.2000 1.2398 37 4.80 1.1804 1.1676 1.1590 1.1961 1.2361 38 4.60 1.1863 1.1730 1.1565 1.1930 1.2308 39 4.40 1.1911 1.1774 1.1528 1.1880 1.2234 40 4.20 1.1950 1.1810 1.1478 1.1814 1.2139 41 4.00 1./975 1.1834 1.1431 1.1733 1.2025 42 3.80 1.2009 1.1851 1.1403 1.1638 1.1891 43 3.60 1.2054 1.1853 1.1385 1.1531 1.1744 44 3.40 1.2083 1.1849 1.1354 1.1415 1.1583 45 3.20 1.2143 1.1900 1.1317 1.1303 1.1408 46 3.00 1.2210 1.2004 1.1257 1.1296 1.1374 47 2.80 1.2363 1.2159 1.1252 1.1354 1.1429 48 2.60 1.2627 1.2362 1.1343 1.1480 1. 1454 49 2.40 1.2870 1.2578 1.1438 1.1596 1.1484 50 2.20 1.3109 1.2791 Ll532 1. 1709 1.1 521 51 2.00 1.3345 1.3000 1.1627 1.1823 1.1618 52 1.80 1.3571 1.3201 l.J 720 1.1934 1.1750 53 1.60 1.3788 1.3394 1.18l2 1.2044 1.1870 54 1.40 1.3992 1.3576 1.1903 1.2153 1.1993 55 1.20 1.4183 1.3746 1.1992 1.2260 1.2116 56 1.00 1.4355 1.3897 1.2075 1.2361 1.2234

    • 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
  • 61 0.00 1.0000 1.0000 1.0000 Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

1.0000 1.0000 Page 8 of 12

CORE OPERA TlNG LIMITS REPORT, FNP UNIT I CYCLE 26 SEPTEMBER 2013 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 I I I I I I I

(.552,225)

I;'

I' 200 I;' (1, 187) =

I' 175 1...01' ~

I;' I' iI""

i"" Banke C 1...01' ~

~ t.; ~

150 iI"" iI""

"t:I

.c:

I...."

iI""

~

~ t.; ~

~

(I)

Co 125 iI""

S i""

~ II t.;

c ~

.,0

'(ij (0,114) iI""

0 100 Q.. ~

..lC ~ BankO C ~

III "t:I 75 L.oI 0

0:: ~

~

i""

50 ~

~

25

, ~

~.

~ (.070,0) i""

o 1 1 1 1 1 1 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 12

CORE OPERA TING LIMITS REPORT, FNP UNIT I CYCLE 26 SEPTEMBER 2013 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1

L

....CJ0 co 0.8 L1.

C) s::

~

co Q,I Q.

".~

Q,I 0.6 IV E Core Height (ft.) K(Z)

L 0 0.000 1.000 z 6.000 1.000 12.000 1.000 N

~ 0.4 FQ = 2.50 0.2 o

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

Page 10 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 26 SEPTEMBER 2013 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOe 120 110

(-12,100) (+9,100) 100 90

~... -_ . . ..

UNACCEPTABLE V ~ I UNACCEPTABLE r--

<< w

~

OPEltATION I \ , -o.P.E.RAIIQN __

0 80 VI ~

Il, oJ ACCEPTABLE

<t

~ 70 L-PfERATIO 1,1 a:

w

I:

I Q 60 I w

-eS0 50

(-25,50)

V II(+24,50) 01 40 3

0 Il, 30 20 10 o

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

Page II of 12

CORE OPERA TlNG LIMITS REPORT, FNP UNIT 1 CYCLE 26 SEPTEMBER 2013 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE

'0... OPERATION I'-. r--.,

660 -......,

i"-...

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

I'--

-""""1'..

i'- ........... """""" -........

-""""r-.,

640 -......,

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

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

~Cl

"" I'---

I'-.

I'-....

r--... I'-.

r--..

~

\ 2425 pslg x...., ...........

r-.... -........ -......, \ 2235 psig

<II

~ 620 ......, ......,

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

Cl

~

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

I'-. I'-....

\ ---&- 1985 psig

-X-1825 pslg 1\

\

600

"" i"--.,

I'-.r-.,

r---

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

I'-. r--.,

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

I ACCEPTABLE I i' ...........

OPERATION l I ~

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

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