ML20087F797

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Rev 1 to Brunswick Unit 2,Cycle 11,COLR
ML20087F797
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 08/08/1995
From: Blom M
CAROLINA POWER & LIGHT CO.
To:
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ML20087F792 List:
References
NUDOCS 9508160027
Download: ML20087F797 (19)
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i dP&L Nuclear Fuels Mgmt & Safety Analysis - File: NF-2202.024 ')

B2Cll Core Operating Limits Report Page 1, Revision 1 l

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l BRUNSWICK UNIT 2, CYCLE 11 .

1 CORE OPERATING LIMITS REPORT AUGUST 1995  ;

Controlled Copy I I

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Prepared By: Michael A. Blom l

.i 1

Approved By:, 24M Date: ?, 7, fr~

Kenneth E. Karcher Manager BWR Fuel Analysis 9508160027 95081o PDR ADDCK 05000324 P PDR

~

CP&L Nuclear Fuels Mgnit & Safety Analysis File: NF 2202.024 Page 2. Revision 1 I B2Cll Core Operating Limits Report LIST OF EFFECTIVE PAGES i

Page(s) Resi h 3, 6-19 0 1-2,4-5 1 1

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File: NF-2202.024 CP&L Nuclear Fuels Mg ; & Safety Analysis Page 3 Revision 0  ;

B2Cll Core Operating Limits Report

)

INTRODUCTION AND

SUMMARY

This report provides the values of the power distribution limits and control rod withdrawal block instrum serpoints for Brunswick Unit 2, Cycle 11 as required by Technical Specification 6.9.3.1. The values of the I Pianar Linear Heat Generation Rate (APLHGR) limits, along with associated core flow and core power adjustment '

factors are provided as required by Technical Specification 6.9.3.1.a. The values of the Minimum Critical Po Ratio (MCPR) limits, along with associated core flow and core power adjustment factors are provided as requ by Technical Specifications 6.9.3.1.b and 6.9.3.1.c. The control rod block upscale trip setpoints and a!

values are provided as required by Technical Specification 6.9.3.1.d. l i

Per Technical Specification 6.9.3.2 and 6.9.3.3, these values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.

f Preparation of this report was performed in accordance with CP&L Nuclear Fuels Management & Safet Quality Assurance requirements as documented in Reference 1.

APLHGR LIMITS The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a func of planar average ext - - 5 given in Figures 1 through 9. These values were determmed with the SAFER /GESTR LOCA methodolog, t 'aed in GESTAR-II (Reference 2). Figures 1 through 9 are to be used when hand calculations are required as specified in Technical Specification 3.2.1.

The core flow and core power adjustments factors for use in Technical Specification 3.2.1 are presented in Figures 10 and 11. For any given flow / power state, the mimmum of MAPLHGR(F) determincd from Figur and MAPLHGR(P) determined from Figure 11 is used to determine the governing limit.

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CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.024 B2C11 Core Operating Limits Report Page 4 Revision ! l MCPR LIMITS ne ODYN OPTION A, ODYN OPTION B, and non-pressurization transient MCPR limits for use in Technical Specification 3.2.2.1 and 3.2.2.2 for each fuel type as a function of cycle average exposure are given in Table 1.

Rese values were determined with the GEMINI methodology and GEXI .-PLUS critic;.1 power correlation described in GESTAR-II (Reference 2) and are consistent with the Safety Limit MCPR of 1.07 specified by Technical Specification 2.1.2. He analysis was performed without End of Cycle-Recirculation Pump Trip (EOC RPT)

operable, ne core flow and core power adjustments factors for use in Technical Specification 3.2.2.1 are presented in Figures 12 and 13. For any given flow / power state, the maximum of MCPR(F) determined from Figure 12 and MCPR(P) determined from Figure 13 is used to determine the governing limit.

ROD BLOCK INSTRUMENTATION SETPOINTS The nominal trip setpoints and allowabic values of the control rod withdrawal block instrumentation for use in Technical Specification 3.3.4 (Table 3.3.4-2) are presented in Table 2. These values were determined consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-II (Reference 2).

REFEP,ENCE(s)

1) CP&L Nucicar Fuels Management & Safety Analysis Quality Assurance File NF-2494.0026.1,

" Preparation c>f the Brunswick Unit 2, Cycle 11 (B2Cl1) Core Operating Limits Report (COLR),

Revision 1,* (August 1995).

2) NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel," (latest approved version).

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2202.024 B2C11 Core Operating Umits Report Page 5, Revision 1 Figure 1 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR UNEAR HEAT GENERATION RATE APLHGR) UMIT VERSUS AVERAGE PL(ANAR EXPOSURE 13 A INH S C 3 .1 g

(

/

\x yj . 7 b FERtilSSIBU:

crmw nr \

@EfiAhiN \

2 10- igugg gun \

@W1/bT) (kW/fti \

v 0,00 10.71 N t:

1 9- E.. N. . I.l. lb

. h, 3

2,20 1 1.01 N 3,31 1 1.10 N E 9,91 1 1.J'l N O 5,51 1 1.4T 5 s-a a' Lar 7,72 g * *'

1 1.71l  :

U:s I i 11 .02 1;t.1 L \

13,78 1 1.9! ,

\

7 16,53 i i.E 22.05 27,56 1 1.01; 10 41'

\ ,

l 35 58 /.T! i 39,21 3.91 6 10,50  !.20 54,22 :5.60

{

$ (

0 5 10 15 20 25 30 35 40 45 50 55 60 l AVERAGE PLANAR EXPOSURE (GWd/MT)

CPbl Nuclear Fuels Wgmt & Safety Analysis File: NF-2202.024 e

82C11 Core Operating Umits Report Page 6. Revision 0 Figure 2 FUEL TYPE BD323A'(GE8X8EB)  :

AVERAGE PLANAR UNEAR HEAT J GENERATION RATE APLHGR UMIT VERSUS AVERAGE PL(ANAR EX)POSURE .

l 14 --

'rHl! .FMUPEti m r.mED10Irr  :

REC 1NCAL SP:CWICA"O 3.2.1 l

13-  %

(

/ N N

i 12- '

FEniitssisu: \ .

' / FEGON OF C PEIATON h\ l i

11 - N F \

N N\  !

{10 >Vs "TT (w/r0 N j 2

3 C.00 j.5]

11 33

]2 j}

%g

  • T g i:3i 11 .02 ii fi 13 14 IJ.78 13 05 16.53 12 72 (

0 22,05 12 04 l 27.56 11 38 33.07 10 75 38.58 10 12 4A no oM L 7 49.60 8 49 55,12 6 02 )

l

' . l 6 l 5

10 15 20 25 30 35 40 45 50 55 60 0 5 AVERAGE PLANAR EXPOSURE (GWd/MT)

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" CP&L Nuclear Fuels Wgmt & Safety Anolysis File: NF-2202.024 B2C11 Core Operating Umits Report Page 7. Revision 0  ;

l Figure 3 i

I FUEL TYPE BD317A (GE8X8EB)  !

AVERAGE PLANAR UNEAR HEAT ~

i GENERATION RATE APLHGR UMIT j VERSUS AVERAGE.PL(ANAR EX)POSURE  ;

i I

14 i Hl. FIMa rI in w r. mtD1 0llY EC##IW. SP :Cil ICA10m 3.2.1  ;

13- #, j f  %

l

/ \

12- \  :

/ Pgum nao r \

i #

s OPlRA 10h Or 5 -l

.11  ;

b  !

m ., .

Ns  !

  • ' r. ..

(Id f/ft)

T .-

[GW$/h(

D 2 C.00 11 23

\ ~

3

, H? lH9 \ >

D2 ii i7  %

11 .02 13 02 \

18.53 12 65 3

, Lt2 0!  !! e6 g l5N i4 0 38.58 1003 4000 e 20 4

49.00 8 37 7 m.u a vi 6- ,,  ;

5-0 5 10 15 20 25 30 35 40 45 50 55 80 AVERAGE PLANAR EXPOSURE (GWd/MT)

' CP&L Nuclear Fuels Mgmt & Sofety Anofysis File: NF-2202.024 B2C11 Core Operating Umits Report Page 8. Revision 0 l

Figure 4 l FUEL TYPE NBD330A (GE8X8NB AVERAGE PLANAR UNEAR HEAT ) ,

GENERATION RATE (APLHGR UMIT i VERSUS AVERAGE PLANAR EX)POSURE i

~

13  :

THit FHUFEtim.r t.citD10I rf i ECiNHlAL SP CIFICA"O 3.2.1 l 12-7  %

3 PERh:lSS BU REGION Y \

11

/ ONAM \ 3 ,

,(

\

N 2 10 i v \

t- \

3 h pCPOStIRE

,GWd/hT)

Ul4 (Id )

x 0 0.00 10 60 b ' '0 'O " \

8- 5.51 11 40 9 8.61 11 56 9.92 12 07 11 ,02 12 24 7

)) 78 ]2 32 23E 27,56 ti65 11 10

)

33.07 10 57 E 'k am

  • 5

'.na 49 60 54.00 7 92 5 91 5- ,

to 15 20 25 30 35 40 45 50 55 60 0 5 AVERAGE PLANAR EXPOSURE (GWd/MT)

1 1

j Flie: NF-2202.024 CP&L Nuclear Fuels Mgmt & Safety Anolysis '

B2C11 Core Operating Umits Report Page e, Revision 0

'- Figure 5 .j FUEL TYPE NBD329A (GE8X8NB AVERAGE PLANAR UNEAR HEAT ) i GENERATION RATE APLHGR UMIT .

VERSUS AVERAGE PL(ANAR EX)POSURE ,

13-THl! FID Et inu r.miD101T l N REC 1NM. SP :CW KW D 3.2.1 '

/ \

12 -

N l FE**"t*8M U

\ ~

FEGI)N'Of \

j

/ cmem \ .

11 , ,

i f f-

\ i

% l n

Ns

  • 10- 3 i

v t= -

e k,

3 f

\

0 C.00 5 90 10 70 11 18 \ 1 1

4 .41 11 46 5.51 11 63 11 ,02 12- 56 13 ,78 1244 18 .53 12 18

'Y ii ,G5 ii e i 1

21 .56 11. 12 r

33.07 10 58 '

38 .58 10 05 N'an !N * >

5(22 5 .0 5 .

O 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT) l

... l File: NF-2202.024

' :CP&L Nuclear Fuels Mgmt & Sofety Analysis B2C11 Core Operating Limits Report Poge 10. Revision 0  ;

Figure 6 FUEL TYPE GE10-P8HXB329-12GZ1-100M-150-T (GE8X8NB-3)- ,

AVERAGE PLANAR UNEAR HEAT l GENERATION RATE (APLHGR) UMIT i VERSUS AVERAGE-PLANAR EXPOSURE ,

.j 14 m as rio me s ie..we Tc or T :CH41 0 LIPOMFNATI* 3.2,1 13

<^ % l

% i

) f '

12- r \

/ mmm N me N 11 .

/ w. m

_ 01 s,  :

^

[ \ l R '

N u

" $s rm or auarr \ '

owi/n4 (m/to N 3

C.00 10 52 h\  !

H2 Mt?

i'.25 i5 91 \

2 .31 11 17 1 4.41 11 35 L 5.51 11 53 \

8 ,,,i ii fi 7.72 11 90 8.82 12 12 9.92 1237

'< no 12 83 (

I '

.75 12 52 18.53 12 65 22.05 12 13 27.56 11 47 -)

w sua in on L 0

  • 49.60 8 63 55.67 5 90

>. 5 15 20 25 30 35 40 45 50 55 60 0 5 10

, AVERAGE PLANAR EXPOSURE (GWd/MT).-

1 i

I

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.. . l CP&L Nuclear Fuels Wgmt & Safety Analysis File: NF-2202.024 l 82C11 Core Operating umits Report Page 11. Revision 0 l

Figure 7  !

FUEL TfPE GE10-P8HXB324-12GZ-70M-150-T (GE8X8NB-3) '

AVERAGE Pl.ANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE I

14- l l

ms nome s m.uisc n av ,

Tl:CH 10L1;PECIFWATDN 3.2.1 l 13- A .

I N i N

- - -\

i 12- J - --- -

{ Uibk5 0SER@N l

l C 11 '

% / N b POSL.lRE UldfT N p(W$/hT)

,G (Mf/ft) K

-:s 10 o.uu iu is to 78 '\

3 C.22 1 .10 10 87 07 k( l

$ 2.20 3.31 11 11 32  % '

9 1.11 11 $2 5.51 E.61 11 12 02 83 }

7.72 12 22 E.82 12 44 8- * "' 70 11 .02 12 96 13,78 13 17 18.53 12 93 22.05 12 27 (

27.56 11 62 \

7- 33,v f ju g, 38.58 10 27 44.09 9 52 49.60 8 78

  • 55.12 6 27 6 l 0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

I

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w CP&L Nuclear Fuels Mgmt at Sofety Anotysis File: NF-2202.024 B2C11 Core Operating Umits Report Page 12 Revision 0 Figure 8 FUEL TYPE GE10-P8HXB320-11GZ-100M-150-T-(GE8X8NB-3)

AVERAGE Pl.ANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT-VERSUS AVERAGE PLANAR EXPOSURE 14-T IIS F10JRE IS re. t.ns TC B T :CHtlCJL!iPE :n ATI"M 3.2,1 '!

13 4

A g J \

lg me m_E '

- i I EG ON OF p gj J A

  1. h .j a'

ME m

Idb im hN 1.10 10 97 f 5 .20 11 10 9

5

.51 11 53 \ 1 E .61 11 68 ,

1 ,72 11 84 8

11 .02 12 33 13.78 1252 18,53 12 40 22.05 11 93 27.56 11 44 (

7 m,v , m.

35.58 1026 44,09 9 47 49 ,60 8 68 55.12 6 15 a' 6

O 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT) -

~--es.e -- ,,._-a,- --,ee- e,-,.+-,s--p- -r,-

. . :. H

' CP&L Nuclear Fuels Mgmt & Safety Anotysis Flie: NF-2202.024 B2C11 Core Operating Umits Report Page 13, Revision'0  ;

i Figure 9 FUEL TYPE GE10-P8HXB322-11GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR UNEAR HEAT- ,

GENERATION RATE (APLHGR) UWT l

VERSUS AVERAGE PLANAR EXPOSURE f 14-T tlS F1GAtt IS nt. uta TC B1 T :CHWCJ L1 PEOF)ATIM 3.2,1  ;

13 T

I N .

NN 1 12- j

[

/ $ IdiiMY OWTKN h  ;

- / N s

g" e a

m m

er a s N N 1.10 5 .20 10 95 11 08 2 .31 11 21 '

9-- i.11 11 ?"

5.51 E .61 11 50 11 67

}

7 .72 11 92 E.82 12 26 8- 12 95 11 ,02 j 13,78 13 12 16.53 12 89 22,05 12 29 (

27.56 11,67 \

7 x,v f iv,,

38.58 10 26 44,09 9 52 49.60 8 78 3 55.12 6 29 j

6 to 15 20 25 30 35 40 45 50 55 60 l 0 5 AVERAGE PLANAR EXPOSURE (GWd/MT) 1

r File: NF 2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 14, Revision 0  ;

- B2C11 Core Operating Limits Report i

Figure 10  :

e Flow - Dependent MAPLHGR Limit, MAPLHGR (F) 1.0 -

so4 ,

gs g

<** g *$

0.9 -

+ 5%

i 0.8 -

MAPLHGRIFl= MAPFACp a MAPLHGR$TO MAPLHGRs70 = STANDARD MAPLHGR UMITS MAPFACF IF)= MINIMUM (1.0. ApWC/100 + Spl 0 .7 W C= % RATED CORE FLOW s

I0.8 MAXIMUM CORS FLOW

(% retedl Ap _ Sp 102.8 0.8784 0.4881 0.8 -, 107.0 0.8788 0.4874 112.0 0.8807 0.4214 117.0 0.8488 0.3828 I I I I I I 0.4 I 80 80 100 110 80 60 70 30 40 CORE FLOW (% totedl This figure is referred to by Technical Specification 3.2.1

. l l

i File: NF 2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 15. Revision 0 B2C11 Core Operating Limits Report i

i Figure 11 l

Power - Dependent MAPLHGR Limit, MAPLHGR (P) l l

l

?

t.0 .

I t 0.9 -

E P

0.8 -

MAPLHGRIP) = MAPFACp'MAPLHGRSTD MAPLHGRSTO. STANDARD MAPLHGR UMITS '

I0.7 s 50% CORE FLOW FOR 2$% >P: NO THERMAL UMITS MOMTORING REQUIREO g

j IE ,,, _ ,

FOR 2s% sP<30%:

MAPFACp = 0.585 + 0.005224 (P- 30%)  !

FOR s 50% CORE FLOW MAPFACp = 0.433 + 0.005224 (P- 30%)

i

> 50% CORE FLOW FOR > 50% CORE FLOW l

0.5 - g g FOR 30% sP:

g e MAPFACp.1.0 + 0.005224 IP- 100%I ,

g i

I I I I I I I 0.4 70 SO 90 100 4 20 25 30 40 50 SO ,

i POWER t% rated L

l This figure is referred to by

)

Technical Specification 3.2.1 l l

1

j. -

I

~~~

CP&L Nuclear Fuels Mgmt & Safe:y Analysis File: NF-2202.024 j B2Cll Core Operating Limi:s Report Page 16 Revision 0  :

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Table 1  ;

MCPR Limits (EOC-RPT Not Required)

Non-oressurization Transient MCPR Limits J

Exposure Range: BOC11 to EOC11 GE8x8NB-3 GE8x8NB-3 BP8x8RE8x8EBE8x8NB GE10-P811XB32412GZ-70M 150-T GE10-P8HXB32211GZ-70M-150-T/ All GE10-P8HXB320-11GZ-100M-150-T/

GE10-P8HXB329-12GZ1-100M-150-T 1.31 1.25 1.20 Pressurization Transient MCPR Limits MCPR - Option A GE8x8NB/GE8x8NB-3 BP8x8R/GE8x8EB Exposure Range: BOC11 to EOC113000 mwd /MT 1.34 1.33 Exposure Range: EOC11-3000 mwd /MT to EOC11 1.35 1.33

{

=i MCPR - Option B f GE8x8NB/GE8x8NB-3 BP8x8R/GE8x8EB Exposure Range: BOC11 to EOC11-3000 mwd /MT 1.27 1.26 ,

- Exposure Range: EOC11-3000 mwd /MT to EOC11 1.31 1.29 )

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' Ibis table is refened to by I Technical Specifications 3.2.2.1 and 3.2.2.2 -

l l

l

File: NF-2202.024 CP&L Nuclear" Fuels Mgmt & Safety Analysis Page 17. Revision 0  !

i B2Cl1 Core Operating Limits Report t

Figure 12 Flow - Dependent MCPR Limit, MCPR (F) i FOR WC 1% RATED CORE FLOW) a40%

FOR WC (% RATED CORE FLOW 1 <40%MCPR(Fl= MAX (1.20. ApW C /100+0pl I MCPRtFl=lApWcil00 + Spl

,- 'I1 +0.0032140-WCII MAX FLOW Ap _ Sp .

,*7 117.0 - 0.832 1.809

  • 112.0 - 0.602 1.747 '

107.0 - 0.588 1.697 101.5 - 0.571 1.655 1.6 -

b MAXIMUM FLOW RATE = 117.0%

1.5 ,. 112.0 %

107.0%

102.5%

i 1.4 - >

1.3 -

1.2 -

I I I I I I I I I 90 100 110 120 1.1 #0 70 30 30 40 50 20

, CORE FLOW (% retodi His figure is referred to by Technical Specification 3.2.2.1

., File: NF 2202.024 '

CP&L Nuclear Fuels Mgmt & Safety Analysis Page 18, Revision 0

. B2Cll Core Operating 1.imits Report t

Figure 13 Power - Dependent MCPR Limit, MCPR (P)

' RATED MCPR MULTIPLIER Kpl r

Oh"CP" v

I 23 -

I:

.n OPERATING LIMIT MCRP (P) = K,

  • OPERATING LIMIT MCPR (100)

" > 50% CORE FLOW FOR P < 25%: NO THERMAL LIMITS MONITORING REQUIRE 0

!  ! NO UMITS SPECIFIED 8- 2.1 -

l I FOR 25% s P s P.,,  :(P,. = 30%)

g g '

K, = MAXIMUM OF 1.481 OR Kw 2.0 - l l s 50% CORE FLOW K = (K , + 0.02 (30% Pil / OLMCPR(1009 f g  ;

- K,,, a 1.9 FOR s 50% CORE FLOW i

  • e. l .9 2.2 FOR > 50% CORE FLOW

" l l I

  1. 3,3 -

O FOR 30% 5 P < 45%:

> K, = 1.28 + 0.0134 (45% Pl 1S ~

l. = . FOR 45% s P < 60%:
  • ! l K, = 1.15 + 0.00867 (60% . PI 1.

1.4 -

l l FOR 60% s P:

g g K, = 1.0 + 0.00375 (100% .Pl

  • t.3 - l g

$ I I f 1

1.2 -

g l Io .. l l l \

I t

I I l I

t t I 70 80 90 100 h1.020 25 30 40 50 60 POWER 1% tetod PavPAss i

' Itis figure is icterred to by Technical Specification 3.2.2.1

-y v y 9 -.

p +%y-

File: NF-2202.024 CP&L Nuclear Fuels Mgmt & Safety Analysis Page 19 Revision 0 B2Cll Core Operating Limits Report 1

l l

Table 2 l

RBM System Setpoints Trio Setooint Allowable Value Setpoint  ;

27.0 s 29.0 low Power Setpoint (LPSP')

62.0 s 64.0 Intermediate Power Setpoint (IPSP')

82.0 s 84.0 High Power Setpoint(HPSP')

s 115.1 s 115.5 low Trip Serpeint (LTSP*)

s 109.3 s 109.7 Intermediate Trip Setpoint (ITSPS) ,

s 105.5 s 105.9 High Trip Serpoint (HTSP*)

s 2.0 seconds s 2.0 seconds to >

  • Serpoints in percent of Rated 'Ibermal Power.
  • 115.1/125.0 of full ,

Setpoints relative to a full scale reading of 125. For example, s 115.1 means s i

scale.

1 0

1

' Ibis table is referred to by Technical Specification 3.3.4 (Table 3.3.4-2)

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