ML20067E361

Rev 0 to Brunswick Unit 1,Cycle 8 Core Operating Limits Rept

ML20067E361
Person / Time
Site:	Brunswick
Issue date:	02/28/1991
From:	Clements T, Devoe M CAROLINA POWER & LIGHT CO.
To:
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ML20067E359	List: ML20067E358 ML20067E361
References
NUDOCS 9102140217
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Text

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CP&L Huclear Fuel Section File: NF-2202.018 Blc? Core Operating Limits Report Page 1, Revision 0 BRUNSVICK UNIT 1, CYCLE 8 CORE OPERATING LIMITS REPORT FEBRUARY 1991 1

Controlled Copy C I Prepared By: M. J. DeVoe Approved By: #

//gu,p ff Datei/2/'//9/

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T. B. Clements Manag6c Transient Analysis l

9102140217 910211 {

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a CP&L' Nuclear Fuel Section File: NP 2202.018 B1CB Core Operating Limits Report Page 2, Revision 0 LIST OF EFFECTIVE PAGES -

Pace (s) Revision 1 15 0 i.

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CP&L Nuclear Fuel Section File: NF-2202.018

-31C3 Core Operating Limits Report Page 3. Revision 0 INTRODUCTION AND

SUMMARY

This report provides the values of the power distribution limits and control rod withdrawal _ block instrumentation setpoints for Brunswick Unit 1, Cycle 8 as required by Technical Specification 6.9.3.1. The values of the A.ERAGE PLANAR LINEAR HEAT GENERATION RATE (APillGR) 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 POWER RATIO (MCPR) limits, along with associated core flow and core powe r adjustment factors are provided as required by Technical Specifications 6.9 3.1.b and 6.9.3.1.c. The control rod i

block upscale trip setpoints and allowable values are provided as required by Technical Specification 6.9.3.1..t.

Per Technical Specifications 693e and 6.9.3.3, these values have been determined using NRC approved metnodo) igy and are established such that all applicable limits of the. plant safety analysis are met.

Preparation of this report was performed-in accordance with CP&L Nuclear Fuel

Section Quality Assurance reouirements as is documented in Reference 1.

-4 APIllGR LTMITS The limiting .AP1JIGR value for the most limiting - lattice (excluding -natural

- uranium) of each fuel type as a function of planar average exposure is given in Figures.1;2,3,4, i...I 5.

These values were determined with the SAFER /CESTR LOCA l methodology describad . in GESTAR II- (Reference 2) . Figures 1,2,3,4, and 5-are used when hand calculations are required as specified in Technical Specification 3;2 l.

i-h The ' core' flow'- and core power. adj ustment factors for .use in Technical

. Specification 3.2' 1 are presented in' Figures 6 and 7. For any given flow / power

.r- state the minimum ' of MAP 111CR(F) . determined from Figure 6 and MAP 1JiGR(P) determined from ' Figure 7 is used to determine the core flow and power adjusted

. governing' limit.

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ri CP&L Nuclear Fuel Section- File: NF-2202.018- i s BIC8 Core Operating Limits -Report Page=4, Revision 0.;

m, .. ..

.MCPR LIMITS The ODYN 0PTION .

7 A,.0DYN OPTION B, and non pressurization transient MCPR limits for use:in Technical Specifications 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. These values were -

= determined with the _ - CEMINI methodology and CEXL PLUS critical power ratio correlation . described L in CESTARill (Reference 2) and are cons! stent with the Safety Limit MCPR'of l'.07 specified by Technical Specifiaation 2,1 2.

4

-The - core flow: and . core- power adj us tment - factors -for use -in 'achnical

' i

- Specification 3.2.2.1:are presented .in Figures 8 and 9. For any given flow / power. -it

state the maximum of MCPR(F) determined from'F1 ure -

5 8 and MCPR(P)-' determine.d from Figure 9 is used to determine the core flow and power . adjusted governing: limit.

RQD BLOCK' INSTRUMENTATION SETPOINTS

- The~ nominal trip'setpoints and~ allowable values of-the control rod withdrawal

~

block! instrumentation-for--use in Technical Specification.3.3.4<(Table 3.3.4-2)

., Mare. presented in Table 2;- These values were determined consistent with the bases  ;[

Lof;Jthe 3A RTS program1 and tnef determination, of -MCPR limits . with the - GEMINI .

. methodology and CEXL PLUS critical power ratio correlation described in CESTAR-II M

-(Refe'rence 2)~.

n REFERENCE (s) 4

'- ~

y 1)- CP&L Nuclear Fue1 Section -Quality Assurance- File NF 2491.0006,

" Preparation.oflthe. Brunswick Unit 1,--Cycle-8-Core Operating-l 3- Limits Report", February 1991.

g. .

2).LNEDE-24011 P-A,:." General. Electric Standard Application for g

Reactor' Fuel"-(latestLapproved version). '

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CP&L Nuclear Fuel Section File: NF-2202.018 B1C8 Core Operating Limits Report Pcge 5, Revision 0 Figure 1 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE Pt.ANAR EXPOSURE 13 _ _ _ -

THIS FIGURE IS! REFERRED TO BY

,_ TECHNICAL : SPECIFICATION 3.2.1 12.2 12.3 12;1

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CP&L Nuclear Fuel Section File: NF-2202.018 81C8' Core Operating Limits Report Page ' 6, Revision 0 Figure 2 FUEL TYPE BD3238 GE8X8EB AVERAGE PLANAR LIN(TAR HEAT)

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. CP&L Nuclear Fuel Section File: NF-2202.018 91CB . Core Operating Limits Report Page 7, Revision O Figure 3 FUEL TYPE BD339A (GE8X8EB)

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CP&L Nuclear Fuel Section Fhr NF-2202.018 B1C8 Core Operving Umits Report Po ,e 8, Revision 0 Figure 4 FUEL TYPE GE10-P8HXB322-11GZ-70M-150-T (GE8X8NB-3)

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CP&L Nuclear Fuel Section File: NF-2202.018 91C8 Core. Operating Limits Report Page 9, Revision 0 Figure 5 f'UEL TYPE GE10-P8HXB324-12GZ-70M-150-T (GE8X8NS-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 , ,

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P dPE,L 4;uclear Fuel Section File: .NF 2202.018 BICSl Core Operating 1.imits Report . Page 10, Revision 0 Figure 6 Flow Dependent-MAPMGR Limit, MAPLHCR (F)

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s0q? a O + q'*

9%

sf 0.9 -

3 / '

f.< 0.8 - / *A 3

MAPLNGRIF)=MAPFA;p MAPLHGRSTD- '

-h MAPLHGRSTD = STANDARD MAPLHGR LIMITS  !

0' / MAPFACp(Fl= MINIMUM (1.0. ApWC /100 + Bpl 0,7 ...

b g W C= % RATED CORE FLOW -

e k.0,6 -

-~ 3 MAXIMUM L ' CORE FLOW

-(% tated) .Ap' Sp

'0. 6 - 102.5 0.6784 O.4861 =

,107.0- 0.6758 0.4574 +

L 112.0 0.6807 ;0.4214 1')

117.0 0.6886 0.3828  ;

a j I I' l I I I l

• 0._.4 .

L 30 -' 40- 50 60 70 80 : 90 <100 110-CORE FLOW (% rated)-

?

This figure.is referred to by Technical Specification 3.2.1 Ir t ,

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1

+

e

.-. y CP6L Nuclear Fuel Section File: NF 2202.-018 '

B1CB Core Operating Limits Report Page 11,. Revision 0-t[

Figure 7- I Power - Dependent MAPWGR Limit, MAPMGR -(P) I i

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nr I

t 0,9 -

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'gl MAPLHGRIP) = lUAPFACp'MAPLHGRSTD  ;

^

x<

s' O.? s 50% CORE FLOW MAPLHORSTD* STANDARD MAPLH.GR LIMITS 4

-s" 3 FOR 25% >P. NO THERMtd., LIMITS MONTTORING , i E

w.

.REQU RED ' l l'

O 0.6 ,

1 FOH 25% s P< 30%i

- bc L MAPFAC640 SBS + 0.005224 (P-30%)

.; O ; - FOR s 50% CORE FLOW j,i

'l' MAPFACp r o.433 + 0.005224 (P- 30%)

' -y i p

-1 > 50% CORE A OW .j '

FOR.> 60% CORE FLOW O.5 -

l .

Ji s  % -g # t OR 30% sP;-

l MAPFACp = 1.0+ 0.005224 (P- 100%I . ';

I 1

_l_ ,

, o,4 l 'l l l' 1: -l l ,l

':.,., 20 ' 25 30 40 '50 60 70 - cB0 90: 100  !!'

POWSR tt, rated)

4. ' 4 3lh - ;1: o .

sy :.g. >

s This figure is referred to by  :

Technical Specification 3.2.'l .j-

+

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s. j2 .+., , . . . .. . - - , , . - , . - ,,

CP&L Nuclear Fuel Section File: NF-2202.018

-BIC8 Core Operating Limits Report Page 12, Revision 0 TABLE 1 MCPR LIMITS II Non-Pressurization Transient M';PR - 1.27 (CE8X8NB 3, CE8X8EB, and BP8X8R fuel types)

Prossurization Transient MCPR MCPR MCPR Option A Option B Fuel Type Fuel Type Exposure Ranto GE8X8NB-3 CEBX8EB BP8X8R GE8X8NB-3 CE8XiEl - Ef 8'(88 BOC8 to EOC8-2000 MVD/ST 1.34 1.34 1.34 1.27 L 17 1. 2:1 EOC8-~2000 MVD/ST to EOC8 1.39 1.38 1.38 1.35 1.34 l'.34 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2 l l x i.

l' l-l' t

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s

., g 4

CP&L Nuclear Pdel Section File: - NF-2202.018

-iB1C8 Core Om atin6 Limitt Report Page 13, Revision 0 '

4

. Figure 8 Flow - Dependent MCPR Limit, MCPR(F)

FOR WC (% RATED CORE FLOW) <40% - FOR WC (% RATED CORE FLOW) a 40%.

MCPatF).(Ap?/C1100 + BF) MCPR(F)= MAX (1.20, AFWC/100 + 0p) a *(1 + 0.0C33 (40- WC II .

MAX FLOW -Ap Sp-1I7,0 0.632' 1.809 112.0 -f) 602 1.747 4 1.6 -

107.0 -0.586 -1.697 1024 -0.571 1.655 r,

t

1.5 -

' MAIIMUM FLOW RATE n 117.0%

, T ' 112.0 %-'

f 2-

/ #[.107.0% -101;5 % '

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+

e

3

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_4_- l l l' -l 20 '30 40 i50 60 70 60 90- 100 '110 '12C CORE FLOW t% rettd) i .t i;

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i . r,s .-

1 This-figure is referred to by L' Technical Gpocification 3.2.2.1 g ;+ ,.

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=CP6L Nuclear Fuel-Section- File: NF 2202.018 '

BlCB Core Operating Limits Report Page 14, Revision 0. .

s Figure 9 Power - Dependent MCPR Limit, MCPR(P)

[

-i

RATED MCPR MULTIPLIER IKpl =

2 I I_

w 2.3 - ,

-g. g, . OPERATING LIMIT MCPR (P)= Kp* OPERATING LIMIT MCPR (1001

> 50% CORE FLOW

-o e 22 -

l FOR P< 25%: NO THERMAL LIMITS MONITORING REQUIRED ~

"'. .l l~ ' NO LIMITS SPECIFIED 2',1 --

l l

FOR 25%-5P<PBYPASS: (PBYPASS = 30%)

g; I l=

y 210 ---

.k -l ' KP* lKBYP + 0.02 (30% - Pil/OLMCPR (1001

$- I- g s 50% CORE FLO%V Kgyp= 1.9 FOR 5 50% CORE FLOW

. g 3,9

l. -

= 2.2 FOR > $0% CORE FLOW

.w-l .- )

g, FOR 30% s P< 45%:

~

~l Kp = 1.28 + 0.0134 (4 5% - P)

.u  ? g'a .

l ~ n. .; 1.5 - FOR 45% 5P< 60%: ,

e >==

O l, .l Kp = 1.15 + 0 00867 (60% -P)

h # ~'

!' I FOR 60% sP;-

E

-1

! l \ Kp= 1.0 + 0,00375 (100% P)I

- 1. 3 .

j .N

$ ~ 1.2 - ) -l te If5 g- .- l l

-) . - u -

l- l l- f e' ec .; _l- 1

- "Q,j.o i f 1- ~l 1 -1 I .,

20 25 30: 40 50 60- 70. 80- 90 100

.jj P BYPASS _ - POWER (% rated)

,p i , ,

This figure is referrod to by <

Technical Specification 3.2.2.1 l

[

?

v z..__. . - .- . - . . . . .. .,. ,, , ..~.

CP'$LNuclearFuelSection File: NF-2202.018 B1C8 Core Operating Limits Report Page 15, Revision 0 TABLE 2 RBM SYSTEM SETPOINTS Setcoint Trio Setpoint Allowable Value Low Power Setpoint (LPSP') 27.0 5 29.0 Intermediate Power Setpoint (IPSP') 62.0 $ 64.0 High Power Setpoint (HPSP') 82.0 s 84.0 Low Trip Setpoint (LTSPb) $ 115.1 s 115.5 Intermediate Trip Setpoint (ITSPb) f 109.3 5 109.7 i

.High Trip Setpoint (HTSP ) b

$ 105.5 s 105.9 td2 $ 2.0 seconds 5 2.0 seconds Setpoints in percent of Rated Thermal Power, b

Setpoints relative to a full scale reading of 125. For example, $ 115.1 means 5 115~.1/125.0 of full. scale.

2 >

l 5

l l

This table is referred to by

Technical Speciftention 3.3,4 (Table 1.3.4-2) i D

_