NL-13-1005, Cycle 23 Core Operating Limits Report

From kanterella
Jump to navigation Jump to search
Cycle 23 Core Operating Limits Report
ML13130A057
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 05/09/2013
From: Pierce C
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
NL-13-1005
Download: ML13130A057 (30)
v • d • e


Text

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

40 Invemess Center Parkway Pos t Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 SOUIHERNA COMPANY May 9, 2013 Docket Nos. : 50-364 NL-13-1005 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Unit 2 Cycle 23 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 Reports (COLRs) for Joseph M. Farley Nuclear Plant (FNP) Unit 2 Cycle 23, Versions 1 and 2.

Version 1 was implemented prior to Cycle 23 core load (April 2013). In order to compensate for a preliminarily identified departure from nucleate boiling ratio (DNBR) margin issue that could have reduced DNBR margin for Unit 2 to a negative value later in the cycle, Version 2 of the COLR was issued (April 2013) to conservatively lower the minimum value for acceptance criteria for the measured Ffl/ after 10,000 MWD/MTU. Version 2 was implemented prior to entering Mode 2, and is the currently implemented Version .

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

Sincerely, CR. Pierce Regulatory Affairs Director CRP/RMJ/lac

Enclosures:

1. Core Operating Limits Report for FNP Unit 2 Cycle 23 Version 1 (no longer current)
2. Core Operating Limits Report for FNP Unit 2 Cycle 23 Version 2

U. Nuclear Regulatory Commission NL-13-1005 Page 2 cc: Southern Nuclear Operating Company Mr. Kuczynski, Chairman, President &

Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. J. Adams, Vice President - Fleet Operations CFA04.054 Mr. V. M. Regional Administrator Ms. E. A. Brown, NRR Project Manager - Farley Mr. K. Niebaum, Senior Resident - Farley Mr. J. R. Sowa, Senior Resident - Farley

Joseph M. Farley Nuclear Plant Unit 2 Cycle 23 Core Operating limits Report Enclosure 1 Core Operating limits Report for FNP Unit 2 Cycle 23 Version 1 (no longer current)

SOUTHERN COMPANY A

Energy to Serve Your World'"

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 .. Cycle 23 Version 1

1.0 Limits (COLR) for FNP UNIT 2 has been to with the requirements of Technical S.6.S.

Technical Requirement affected report is listed below:

13.Ll SHUTDOWN MARGIN - MODES 1 2 (with ~ 1)

The aUI:;cH:a by this are listed below:

2.1.1 Reactor Core for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with <1),3,4andS 3.1.3 Moderator Temperature Coefficient 3.1.S Shutdown Bank Insertion Limits 3.L6 3.2.1 Heat Flux Hot Channel Factor (Z) 3.2.2 Nuclear Enthalpy Rise Hot Chan nne 1Factor - f:~

3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature ,tj,T (OT,tj,T) and Overpower Sf (OPuT) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters Pressure, RCS and Total Flow Rate 3.9.l Boron Concentration 1 of 12

parameter for the listcd in 1.0 are presented in limits have been developed using NRC-approved methodologies, including those specified in Technical Specification 5.6.5.

2.1 13.1.l) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent L1k/k.

2.2 (Specification 3.1.1) 2.2.1 Modes 2 (kef1' < 1.0), 3 and 4 The SHUTDOWN MARGIN shall be crrp*"tl than or equal to 1.77 L1k/k.

Mode 5 The SHUTDOWN MARGIN shall be than or equal to 1.0 ,-,,,,,,,vIA< ~k/k.

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

The BOLIARO-lVITC be less than or equal to +0.7 x 10'4 i\k/k/oF for power up to 70 percent RTP with a linear ramp to 0 ~k/ldoF at 100 RTP.

The EOLIAROIRTP-MTC shall be less than -4.3 x 10.4 ~k/k;oF.

MTC limits arc:

300 ppm! ARO/RTP-lVITC should be negative than or equal to

-3.65 x to'4 The 100 ppmlARO/RTP-MTC should be than -4.0 x i\k/k/oF.

where: SOL stands for of Cycle Life ARO stands for All Rods Out EOL stands for End of Cycle RTP stands for RATED THE&\1AL POWER 2.4 (Specification 3.1.5) 2.4.1 The shutdown banks shat! be withdrawn to a position greater than or equal to 225 steps.

2 12

2.5 =~==",-===c:...=== (Specification 3.1.6)

The control rod shall be in physical as shown in Figure 1.

2.6 ~~~,-",,,-,~"-.!.!,,,~~..~~ - FQ (Z) (Specification 1) 2.6.1 (Z) $ *K(Z) forP 0.5 P

FQ(Z) $ *K(Z) p ~ 0.5 0.5 THERMAL POWER where: ==

RA THERMAL POWER 2.6.2 =

2.6.3 is provided in Figure 2.

  • K(Z)

F(Z)$--=---- for P 0.5 Q P*W(Z)

  • K(Z) for P ~ 0.5 (Z) $ 0.5
  • W(Z)

W(Z) values are provided in Table 4.

2.6.6 The (Z) penalty factors are provided in Table L 3 of 12

where: P =- - - - - - - - - -

RATED THERlvfAL 2.7.2 RTF = 1.70 2.7.3 =0.3 2.8 ~=~=':_=-'-'=== (Speci fication 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in 3.

'!£:;!'~~~~!:!.'.i.!~ (Specification 3.9.1) 2.9. L The boron concentration shall be than or equal to 2000 ppm. I 2.10 2.10.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressure shall not exceed the limits specified in 4.

2.11 2.l1.1 The Reactor Trip System Instrumentation Ove!.iemperature t.T and Overpower t.T (OPt.T) setpoint parameter values Table 3.3.1-1 are listed in COLR Tables 2 and 3.

2.12 2.12.1 RCS DNB parameters for pressure, RCS average temperature, and RCS total flow rate shall be within the limits below:

a. Pressurizer pressure 2209 psig;
b. RCS average temperatme :<;; 580.3°F; and
c. The minimum RCS total flow rate 2: 263,400 GPM when using the precision heat balance method 2: 264,200 aPM when the elbow method.

of 0.95 (all in the most rod) and rods out) over the entire cycle. This concentration includes additional boron to B 10 depIction.

4 of 12

Table 1 FQ(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWD/MTU) .Factor 5257 1.0200 5462 1.0223 5666 1.0241 5870 1.0211 6075 1.0200 Notes:

1. Penalty Factor, to be applied to FQ(Z) in accordance with 3.2.1 is the maximum factor which FQ{Z) is expected to over a 39 EFPD interval (sW'Vei11ancc interval of 3l plus allowable extension not to exceed 25% of the interval SR starting from bumup at which the FQ(Z) was deteruum:a
2. interpolation is adequate for
3. For all cycle burnups outside the range of the a penalty 1.020 be 5 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRlL 2013 Table 2 Reactor Trip System Instrumentation - Overtemperature ilT (OTilT)

Setpoint Parameter Values T' ~ 577.2°P pi = 2235 psig K1 = 1.17 K2 = O.017;ap 1<3 = 0.000825/psi

'1 ~ 30 sec '2~ 4 sec 1:4 = 0 sec '5~ 6 sec '6~ 6 sec ft(tlI) = -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 6 of 12

Table 3 Reactor Trip System Instrumentation - Overpower AT (DPAT)

Setpoint Parameter Values T" :::;

K+/-= 1,10 = O.02;oF for '"","LV>' Q,00109/0F T>

= O;oF for decreasing K6 O;oF when T:::;

13 10 sec 1:4 = 0 sec 1:5:::; 6 sec 1:6:::; 6 sec 6(D.I) = 0% all D.I 7 of 12

Table 4 RAOCW(Z)

Axial Point Ell" ,.ltion (feet) 150 MWD/MTU 3000 M'WUIiVI fU I 10000 M\v ULVII e 14000 MWO/MTU 11'1000 MWO/MTU 1 12.00 1.0000 1.0000 1.0000 1.0000 1.\1000 I 2 11.80 1.0000 1.0000 UIOOO 1.0000 1.0000 I i 3 11.60 1.0000 J.OOOO 1.0000 1.11000 1.0000 I I ** ,

4 5

11.40 11.20 1.0000 l.ilOOO 1.0000 1.0000 1.0001) 1.0000

[,0000 1.0000 UlOOO 1.11000

(, 11.00 1.1467 1.1868 1.3012 1.2399 1.2869

! 7 10.80 1.1453 1.1874 1.2782 1.2281 1.2649 I 8 10.60 1.1400 1.1841 1.2514 1.2190 t.2404 9 IOAil 1.1525 l. t804 1.2292 1.2147 1.2196 I 10 JOJ.Q 1.1577 1.11.72 1.2095 1.2117 1.1956 11 10.00 1.1542 1.1733 1.21911 1.2097 1.1851 12 9.80 Ll515 1.1700 1.2277 1.2075 1.1889 13 9.60 1.1488 1.1666 1.2291 1.2030 1.1995 14 9.40 1.1456 1.1610 1.2328 1.2009 I 1.2094 I 15 9.20 1.l~58 1.1539 1.2332 1.20118 1.2169 i 16 9,00 1.1416 1.1450 1.2360 1.2158 1.2269 17 8.80 1.1461 1.1408 1.2442 1.2206 1.2404 18 8.60 1.1590 1.1426 1.2569 1.2317 1.2599 19 8.40 1.1715 1.1539 1.2702 1.2498 1.2833 20 8.20 1.1813 1.1614 1.2796 .1.2633 L3022 21 11.00 1.1887 1.1669 1.2857 1.2738 1.3177 22 7.80 1.1939 1.1705 US8S 1.2815 1.3297_ _ _J 23 7.60 1.1968 1.1720 1.21187 1.2861 1.3381 24 7.40 1.1918 1.1720 1.2858 1.2877 1.3429 25 7.20 1.1981 1.1715 1-2801 1.2865 1.3443 26 7.00 1.1966 1.1695 1.271~ 1.2841 1.3440

~

6.80 1.1934 I.IMI 1.2615 1.2798 1.3411 6.60 1.1888 1.1614 1.2490 1.2731 1.3350 Mil 1.1828 1.1556 1.2347 1.2642 1.3264 6.20 .__lc.1756 1.1490 1.2HI9 1.2534 1.3151 6.00 1.1678 1.1409. ).2013 1.2410. LJOH 5.80 1.1573 1.1368 Ll850 l.Z258 1.2858 I

. 33 5.60 1.1521 1.1374  !.I7tS 1.2124 1.2669 34 SAO 1.1545 1.1474 1.1627 1.2063 1.2475 I 35 5.20 1.1626 1.1558 1.1603 1.2040 1.2379 36 S.OO 1.171.12 1.1634 1.1583 .-~

L2002 1.2352 I 37 4.80 1.1768 1.1705 1.1561 1.1965 1.2324 i 38 .4,60 1.1827 1.1167 1.1540 1.1933 1.2269 39 4.40 1.1876 1.1820 I.ISOS 1.1880 1.21~

I i 40 4.20 1.I913 1.11163 1.1460 1.1812 1.2104 i 41 4.00 1.1966  !.I896 1.1404 1.1129 1.1992

.~.

i 42 3.80 1.2020 1.1918 1.1340 1.1633 1.1863 43 3.60 1.2065 1.19JO 1.1266 1.1526 1.1718 i 44 3.40 1.2102 1.1934 1.1187 1.1409 1.1562 I 45 3.20

- 1.2128 1.1948 1.1153 1.1299 1.1421 46 3.01) 1.2248 1.21)93 1,1196 1.1314 1.1376 47 2.80 1.2476 1.2338 1.1300 1.1423 1.1353 48 2.60 1.2746 1.2552 1.1396 1.1546 1.1348 49 2.40 ___l.:lII06 1.2772 1.l492 1.I663 1.1449 50 2.20 1.3262 1.2989 1.1587 1.1778 1.1575 I 51 2.110 1.3513 1.3198 1.1682 1.1892 1.1700 I 52 1.80 1.3756 1.3409 1.1776 1.2005 1.1824 53 1.60 1.3988 1.3625 US7!) 1.2116 1.1948 54 55

. ~.+*-. 1.4209 1.4413 1.3840 1.4038 1.1%2 1.2051 1,2226 l.nn 1.2072 1.2195 56 l.OIl . 1,4599 1.4215 1.2134 1.2435_ _._ 1.2314 I I

  • 57 0.110 1.0000 1.0000 1.0000 1.0000 1.0000 58 0.60 1.0000 U)OO.IL 1.0000 1.00110 1,0000 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 tUIl 1.0000 1.0000 1.0000 1.01100 1.0000 I
  • 61 O.()O 1.001l0 1.0000 I.OOOIl Top and bottom 5 axial points excluded per Technical Specilication B3.2.1.

1.11000 1.0000 I Page 8 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225

~ (.552,225)

~

~

200 l.;I

~ (1,187) _

~

~

175 ~ IL IL ~

~

Banke C l--' /

3 150 1/ ~

ro ~ ~

"C

.t:

~ l.;I

~ / ~

en ~ ~

- 125 Q.

QI

~ ~

l.;I

.c:

0

'iii 0 100 (0, 114) l.;I

~

~

a.

,:tf. ~ BankO c: ~

ro 00 "C l.;I 0 75 c:: ~

~

l.;I

~

50

~

1/

25 ~

l..t l.I

~ (.070,0) o I I 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 arc 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 OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 Figure 2 K(Z) - Normalized FQ(Z) as a FUllction of Core Height 1.2 1

....0

(.J C1:I LL. 0.8 Ol C

~

C1:I Q) a..

"'C Q)

.~ 0.6 C1:I E Core Height (ft.) K(Z)

' 0.000 0 1.000 z 6.000 1.000 12.000 1.000 g

~ 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 2 CYCLE 23 APRIL 2013 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 w

OPERATION 1/ \

!: 80 0

Il..

...J

E 70 I ACCEPTABLE OPERATION

\

ct:

W J:

~

I-60 J l c

W I

[2 V  ;\

~

0 50

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

QI 40

t 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 11 of 12

Figure 4 Reactor Core Safety Limits 680 660 640 Li::'

Q)

(I)

CI

<ll E. 620 CI ---.t.-1985 psig "I

I -X-1825 psig 600 580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER) 12 12

Joseph M. Farley Nuclear Plant Unit 2 Cycle 23 Core Operating Limits Report Enclosure 2 Core Operating Limits Report for FNP Unit 2 Cycle 23 Version 2

SOUTHERN'\"

COMPANY Energy to Serve Your World'"

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 .. Cycle 23 Version 2 April 2013

1.0 This Core Limits (COLR) UNIT 2 23 prepared in accordance with the requirements of Technical Specification 5.6.5.

Technical Requirement by this report is listed below:

13.1.1 MARGIN - MODES 1 and 2 (with keff ~ I)

The Specifications affected by are listed below:

2.1.1 POWER 3.1.1 2 (with keff < 1),3,4 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Hot Channel Factor (Z)

Enthalpy Channnel Factor-Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature LlT (OTLlT) Overpower (OPLlT) Setpoint for 1-1 3.4.1 RCS DNB Parameters for Temperature, and Total Flow Boron Concentration I of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 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 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 ~kIk.

2.2 SHUTDOWN MARGIN - MODES 2 (with Keff.< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2. 1 Modes 2 (1<eff < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ~k/k.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent ,1.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 10-4 ~k/k/oF for power levels up to 70 percent RTP with a linear ramp to 0 ,1.kJk/oF at 100 percent RTP.

The EOLIARO/RTP-MTC shall be less negative than -4.3 x 10-4 ~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 0-4 ~kJkJoF.

The 100 ppm! ARO/RTP-MTC should be less negative than -4.0 x 10-4 ~k/k/oF.

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 of 12

2.5 =~~~~=~~~!:!:! (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown 1.

(Z) (Specification 3.2.1) 2.6.1 (Z) s *K(Z) forP> 0.5 P

(Z) S

  • forP S 0.5 THERMAL POWER P=---------

THERMAL POWER K(Z) is provided in Figure 2.

  • K(Z) 2.6.4 s~-- for P > 0.5 P*W(Z)
  • K(Z) s --=:;;~--- for P S 0.5 W(Z) are provided in 4.

The FQ (Z) penalty factors are in Table l.

Page 3 12

F/;, (Specification THERMAL POWER P =----------

RATED THERMAL POWER a bumup less than 10000 MWDIMTU, RTP = 1.70.

RTP For a cycle average bumup equal to or (Jrp,.tpr than 10000 MWDIMTU, PFt:Jl = 0.3 2.8 -,-==~=->..=-,-,rr~};;.rr*{~ (Specification 2.8.1 The Axial Flux Difference (AFD) operation are provided 3.

2.9 ~~~~~~~(Specification 3.9.1) 2.9.1 boron concentration shall be than or equal to 2000 ppm. t 2.10 2.10.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits 4.

2.11 2.11.1 Instrumentation Overtemperature LlT (OTLlT) and Overpower for TS Table I-I are listed in 2 and 3.

2.12 2.12.1 DNB nl\n~mp'tf>r" n""'"cll,ri7,,,r pressure, RCS average tpn",\p,.<> and RCS total flow rate shall be within below:

a.

b. RCS  ::;; 580.3°F; and
c. The minimum RCS total flow rate shall ~ 263,400 GPM when using the precision heat balance method and ~ 264,200 GPM when using the elbow tap method.

This concentration bounds the condition ofk.,lf::;; 0.95 (all rods in most reactive rod) and subcriticality (all rods out) over the cycle. This concentration includes additional boron to and depletion.

40f12

1 F Q(Z) Penalty Factor 1 Burnup FQ(Z) Penalty (MWD/MTU) Factor 5257 1.0200 5462 l.0223 5666 1.0241 5870 l.0211 6075 1.0200 Notes:

1. Penalty In with SR 3.2.1 u><t._""".\'U" factor by which is over a EFPD interval (surveillance 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance per SR 3.0.2) from the bnrnup at which the FQ{Z) was determined.
2. Linear interpolation is adequate for intermediate cycle bumups.
3. For all bumups outside the of the table, a penalty factor 1.020 shall be used.

5 of 12

Table 2 Reactor Trip System Instrumentation - Overtemperature (OTAT)

Setpoint Parameter Values 5577.2°F

= = 0.017/  :::; O.000825/psi 1:12: 30 sec 1:254 sec 1:4 0 sec 1:556 sec h(8l) = -2.48 + (qt - qb)} when (qt - qb) 5 RTP 0% ofRTP when RTP < (qt -qb) 15% RTP 2.05 {(qt - qb) -lS} when (qt - qb) >

Page 6 of 12

CORE OPERATING LWITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values K4= 1.10 Ks = 0.02;oF for increasing Tavg K6 = 0.00109;oF when T > T" Ks = O;oF for decreasing Tavg K6 = O;oF when T ~ T" 1:3 ~ 10 sec 1:4 = 0 sec 1:5 ~ 6 sec 1:6~ 6 sec h(M) = 0% RTP for all ill Page 7 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRlL 2013 Table 4 RAOCW(Z)

Axial Point Elevation (feet) 150 MWO/MTU 3000 MWO/MTU 10000 MWO/ MTU 14000 MWO/ MTU 18000 MWO/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 6

7 11.20 11.00 1.0000 1.1467 1.0000 1.1868 1.0000 1.3012 1.0000 1.2399 1.0000 1.2869 10.80 1.1453 1.1874 1.2782 1.2281 1.2649 8 10.60 1.1460 1.1841 1.2514 1.2190 1.2404 9 10.40 1.1525 1.1804 1.2292 1.2147 1.2196 10 10.20 1.1577 1.1779 1.2095 1.2117 1.1956 11 10.00 1.1 542 1.1733 1.2198 1.2097 1.1851 12 9.80 1.1515 1.1700 1.2277 1.2075 1.1889 13 9.60 1.1488 1.1666 1.2291 1.2030 1.1995 14 9.40 I.l456 1.1610 1.2328 1.2009 1.2094 15 9.20 1.1458 1.1539 1.2332 1.2088 1.2169 16 9.00 1.1416 1.1450 1.2360 1.2158 1.2269 17 8.80 1.1461 1.1408 1.2442 1.2206 1.2404 18 8.60 1.1590 1.1426 1.2569 1.2317 1.2599 19 8.40 1.1715 1.1539 1.2702 1.2498 1.2833 20 8.20 1. 1813 1.1614 1.2796 1.2633 1.3022 21 8.00 1.1887 1.1669 1.2857 1.2738 1.3177 22 7.80 1.1939 1.1705 1.2888 1.2815 1.3297 23 7.60 1.1968 1.1720 1.2887 1.2861 1.3381 24 7.40 1.1978 1.1720 1.2858 1.2877 1.3429 25 7.20 1.1981 1.1715 1.2801 1.2865 1.3443 26 7.00 1.1966 1.1695 1.2719 1.2841 1.3440 27 6.80 1.1934 1.1661 1.2615 1.2798 1.3411 28 6.60 1.1888 1.1614 1.2490 1.2731 1.3350 29 6.40 1.1828 1.1556 1.2347 1.2642 1.3264 30 6.20 1.1756 1.1490 1.2189 1.2534 1.3151 31 6.00 1.1678 1.1409 1.2013 1.2410 1.3014 32 5.80 U573 1.1368 1.1850 1.2258 1.2858 33 5.60 1.1521 1.1374 1.1718 1.2124 1.2669 34 5.40 1.1545 1.1474 1.1627 1.2063 1.2475 35 5.20 1.1626 1. 1558 1.1603 1.2040 1.2379 36 5.00 1.1702 1.1634 1.1583 1.2002 1.2352 37 4.80 1.1768 1.1705 1.1561 1.l96S 1.2324 38 4.60 1.1827 1.1767 1.1540 1.1933 1.2269 39 4.40 1.1876 1.1820 1.1505 1.1880 1.2196 40 4.20 1.1913 1.1863 1.1460 1.1812 1.2104 41 4.00 1.1966 1.1896 1.1404 1.1729 1. 1992 42 3.80 1.2020 1.1918 1.1340 1.1633 1.1863 43 3.60 1.2065 1.1930 1.1266 1.1526 1.1718 44 3.40 1.2102 1.1934 1.1187 1.1409 1.1562 45 3.20 1.2128 1.1948 1.1153 1.1299 1.1421 46 3.00 1.2248 1.2093 1.1196 1.1314 1.1376 47 2.80 1.2476 1.2338 1.1300 1.1423 1.1353 48 2.60 1.2746 1.2552 1.1396 1.1 546 1.1348 49 2.40 1.3006 1.2772 1.1492 1.1663 1.1449 50 2.20 1.3262 1.2989 1.1587 1.1778 1.1575 51 2.00 1.3513 1.3198 1.1682 1.1892 1.1700 52 1.80 1.3756 1.3409 1.1776 1.2005 1.1824 53 1.60 1.3988 1.3625 1.1870 1.2116 1.1948 54 1.40 1.4209 1.3840 1.1962 1.2226 1.2072 5S 1.20 1.4413 1.4038 1.2051 1.2333 1.2195 56 1.00 1.4599 1.4215 1.2134 1.2435 1.2314

  • 57 0.80 1.0000 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000 59 60 61 0.40 0.20 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
  • Top and bottom 5 axial points excluded per Technical Specification 83.2.1.

Page 8 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 I I LI (.552,225)

, 1.1 200 I...;

, 1.1 (1,187) _

.~

...; 1.1 175 / ~

~

"2

~

E 150 , 1.1 1..",

Banke

, !.I "C

.£:

~ /

/

[...;

,... ~ ~

til

~

a.

Q) c:

0 125

~

(0, 114) ,...

w
  • iii 0 100 iLl D..

..II:

c:

III

, i.I" Bank 0 en "C [...;

0 15 D:: 1.1

~

50 1.1 25

, 1.1

~.

, (.070,0)

,... 1 11 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 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

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 Figure 2 K(Z) - Normalized F Q(Z) as a Function of Core Height 1.2 1

-L.

0 0

C'II LL C) 0.8 C

~

C'II Q) a..

'0 Q)

.~ 0.6 C'II E Core Height (ft.) K(Z)

L.

0 0.000 1.000 z 6.000 1.000 12.000 N

~ 0.4 1.000 FQ =2.50 0.2 o

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

Page 10 of 12

CORE OPERATING LIIv1ITS REPORT, FNP UNIT 2 CYCLE 23 APRlL 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

/ ~ UNACCEPTABLE OPERATION OPERATION i?

UJ 3: 80 / \

0 0..

...J c(

E 0::

UJ

t:

I 70 60 J I

I ACCEPTABLE OPERATION

~ ,

c UJ

~

- 0 50

(-30,50)

I \(+24,50)

~

e....

Q) 40

~

0 0..

30 20 10 o

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

Page 11 of 12

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 23 APRIL 2013 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE 10.". OPERATION J"'-..- ,.,..,.,

660 f'..

i' r-......

10... l"""'- J"'-..

l"""'- ~

i'-~ I"--

~ i'- i'-

640 I"---j..,. r.....

l"""'- i'- r----. l"""'

["-.., r---.,

i'-- r----. i'-- ~

I"--- 1'-.., ~

iL l"""' t-...... f'..

(I) I"--- J">.., 1\ ---<'- 2425 psig l!! . . . . 1"---

CI x.." i""'"

l"""'- l"'->.. \ - 2235 psig (I)

E!. 620 i'- .......

J"-." ."" ............

CI r:.

J"-." J"'-..-

I'- J"'-..-

r----. l'-.- \ -~1985psig

-x-1825 psig I'- I"...... r----. I"--.. 1\

I"--- 1"--. i'- \

I"--..

t'- r..... f"-,

600 r--....

J".., -.........

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

I"-....

I ACCEPTABLE I i"- t:'--..

OPERATION I 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

Retrieved from "https://kanterella.com/w/index.php?title=NL-13-1005,_Cycle_23_Core_Operating_Limits_Report&oldid=2520734"