ML20086E651

Rev 0 to Brunswick Unit 2,Cycle 10 Core Operating Limits Rept

ML20086E651
Person / Time
Site:	Brunswick
Issue date:	10/31/1991
From:	Devoe M, Karcher K CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20086E648	List: ML20086E647 ML20086E651 ML20086E656
References
NF-2202.020, NF-2202.020-R, NF-2202.020-R00, NUDOCS 9112020233
Download: ML20086E651 (16)

Text

. . .

, n ENClhSURE 1 BRUNSVICK STEAM ELECTRIC PLANT, UNIT 2 NRC DOCKET NO. 50 324 OPERATING LICENSE No. DPR 62 CORE OPERATING LIMITS REPORT REVISION 0 OCTOBER 1991 9112O20233 911121 PDR fiDOCK 03000324-

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i CP&L Nuclear Fuel Section File: NF 2202.020 B2C10 Core operating Liinits Report Page 1. Revision 0 BRUNSWICK UNIT 2, CYCLE 10 CORE OPERATING LIMITS REPORT OCTOBER 1991 Controlled Copy [_ b Prepared By: M. J. DeVoe

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Approved By: .-

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K. E. Karcher Manager s

Incore Analysis

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CP&L 11uclear fuel Section File: NF 2202.020 B2C10 Core Operating Limits Report Page 2 Revision 0 l t

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CP&L Nuclear Fuel Section File: NF.2202.020 B2C10 Core Operating 1.linita Report Page 3, Revision 0 INTRODUCTION AND

SUMMARY

This report provides the values of the power distribution liinits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 10 as required by Technical Specification 6.9.3.1. The values of the AVERACE PIANAR LINEAR HEAT CENERATION RATE (APUICR) limits, along with associated core flow and core power adjustment factorn are provided as requsred by Technical Specification 6.9.3.1.a. The values of the MINIMUM CRITICAL. POWER RATIO (MCPR) litsits, along with associated core flow and core power adjustinent factors are provided as  ;

required by Technical Speelfications 6.9.3.1.b and 6.9.3.1.c. The control rod block upscale trip setroints and allowable values are provided as required by Technien1 Specification 6.9.3,1.d. ,

Per Technical Specifications 6.9.3.2 and 6.9.3.3, these values have been determined using NRC approved roethodology and are estabitshed suen that all applicable limits of the plant safety analysis are tuet.

Preparation of this report was performed in accordance with CP&L Nuclear Fuel Section Quality Assurance requirements as is documented in Reference 1.

APUICR LIMITS The limiting APUICR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar avercge exposure is given in Figures 1,2,3,4, $. and 6. These values were deterinined with the SAFER /CESTR 1DCA methodology described in CESTAR II (Reference 2). Figures 1,2,3,4,5, and 6 are used when hand calculat. ions are required as specified in Technical Specification 3.2.1.

The core flow and core power adjus tment factors for use in Technical Specification 3.2.1 are presented in Figures 7 and 8. For any S iven flow / power state the minimum of MAPUICR(F) determined froin Figure 7 and MAPulGR(P) determined from Figure 8 is used to deterinine the govarning limit.

F

,.e-,---pe-#ww,y,.,-,y- = 9 ee w- , ,e.=y,,g,a,e,,...,w 3ug v * ,- . %,g,-m% a,w q y, es;my,, e g % g p r. .

,w3..,,e.n-,.yp,--.-sep4,.q- e.e,c,,-.,y, -=.4 -=,%.p.,-w , , . --_,.,,,vyw.em.g + - + , - . ',4-..se-wed-_iu-es

0 0 CP&L Nuclear Fuel Section File: NF 2202.020 B2C10 Core Operating Limits Report Page 4 Revision 0 MCPR LIMITS l

The ,0DYN OPTION A, ODYN OPTION B, and non pressurization transient MCPR litaits

' 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 CEMIN! methodology and GEXL Pl.US criticel pwer correlation described in CESTAR 11 (Reference 2) and are consistent with the Safety Limit MCPR nf 1,07 specified by Technical Specification 2.1 '

i l

The core flow and core power adjustment factors for use in Technical {

Specification 3.2.2.I are presented in Figures 9 and 10. For any given flow / power state the maximum of MCPR(F) determit.ed from Figure 9 and MCPR(P) detertained from Figure 10 is used to determine the governing limit.

P.0D BLOCK INSTRUMENTATION SETPOINTS l

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) are presented in Table 2.

These values were determined consistent with the bases of the ARTS prograin and the deterininatton of MCPR limits with the GEMINI methodology and CEXL PLUS critical powet correlation described in CESTAR II (Reference 2).

REFERENCE (s)

1) CP6L Nuclear Fuel Section Quality Assurance File NT 2491.0055,

" Preparation of the Brunswick Unit 2. Cycle 10 Core Operating Limits Report", October 1991.

2) NEDE 24011 P A, "Ceneral Electric Standard Application for Reactor Fuel" (latest approved version),

i

,.,s.4,.,m_..#.._.,w. ,.,.%_,___,,_, ___,,.__.,..m..... _.,%..... .. % . ._, ,, m,.,,.,,#,.m.,.x.,,,._,v__.,._.,, ,~_,_,.,_,_,._,..,.,,_.a

.. - .=. .- -. - --. - - _ - - . --- --. - . . - - . -

CP&L Nucl:or Fuct Ssetton File: NF-2202.020 a

• B2C10 Core Operating Limits Report Page 5, Revision 0 Figure 1 FUEL TYPE BP8DRB299 (BPBX8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR LIMIT VERSUS AVERAGE PL(ANAR EX)POSURE F i l l l l j I Tills FIGURE IS REFERRED TO BY TECHNICAL SPECIFICpilOh 3.2.1 l l

! 12[2 i T 12

/ N I 11 ,5 11.0 g 11 0 N 11 - -

/

v PERMISSIBLE 10.9 REGION 10F g OPERATION l ~

3 K 40.3 5

I 10 = --

- - + - l\-

\

N 9- ,

9.0 8- ,

, j , , , ,- p 0 5 10 15 20 25 30 35 40 45 AVERACE PLANAR EXPOSURE (GWd/ST)

CP&L Nucl:or Fuci Ssetion File: NF-2202.020 B2010 Core Operating Limits Report Page 6, Revision 0 Figure 2 FUEL TYPE BD317A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR LIMIT VERSUS AVERAGE PLANAR EX)POSURE

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l i l l l l TiilS FIGURE S REFEliRED' TO DY

,  ;  ! TECHNICAL SRECIFICATION 3.2.5 13 -- " '

d  !  ! I i

13.02 IN j 12.57 I 12.65 ! '

i 12.07 , i .,3 i 11 30 11 11f32 !\

• 11j23 7

h PERMISSI81!E

!ON OR 1C.67

• 10- '

OPERAT1DN H

g 10.03 g  ! N i

l 9.2D \

% e -- -

8- 37\

7= t 6=

n 5.91 5 i j i; , j i , -i l 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST) l

CP&L Nuclear fusi Section File: NF-2202.020 B2C10 Core Operating Limits Report Page 7. Revision 0 Figure 3 FUEL TYPE BD323A AVERAGE PLANAR LIN(EAR HEATGEBX8EB)

GENERATION PATE APLHGR) UMIT VERSUS AVERAGE PL(ANAR EXPOSURE 14 -- - - --

TKIS FIGORE S REFERRED TO BY 13.1 A TECHNICAL. SPECIFICATION 3.2. 1 I

13 -- ,

l12.f 9 12.72 12.62  ;

12 / 12'#I l -  !

, 33 \

33 11.38 l\

C h

PGRMi$SIBLE 10,75 \

" 10- REGION OR Kc.

OPERATION 10.12 N

T g_ 9.31 \ ^

8-i 7- \

6-6.02 5 , j ,  ; , ,  ;

i O S 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST) e - -r ---g ,w , y ---m= , e a,- ,- - - - ens--- , ~ :r

CP&L Nucisor Fuel Section Film: NF-2202.020 B2C10 Core Operating Limits Report Page 8. Revision 0 -

Figure 4 FUEL TYPE NBD329A (GE8X8NB)

AVERAGE PLANAR UNEAR HEAT

' GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE l  !

' { l I THIS FIGLRE S REFERRED TO BY j TECHNICAL SPECIFICATION 3.2. 1 12-  ! b I i

PERMISSIBLE l \

jREGION IOF 33

/ IOPERATION

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• O 10-h s \

b g- <

b 5 BXPO'URE  !-

L!dlT l (GWo/ST)

(kW{ft) _

Q g 0.00 2-00 10.10 11.18

\%

0. 4.00 11.46

< 5.00 11.63 10.00 12.56 12.50 12.64 15.00 12.18

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30.00 10.58 35.00 10.05 40.00 9.04 6 4^ 00 " 0?

49.19 5.10 4 i;

O 5 10 15 20 25 30 35 40 45 50 AVERAGE Pm.NAR EXPOSURE (GWd/ST)

4 CP&L Nucl:or Futi Section File: NF-2202.020 P2010 Core Operating Umits Report Page 9. Revision 0 Figure 5 FUEL TYPE NB')330A (GE8X8NB AVERAGE P! A:4AR LINEAR kEAT )

GENERATION RATE APLHL'O UMIT VERSUS AVERAGE PL(ANAR E2POSURE 13- .

l l l THIS FIGORE S REFERRED T') BY TECHNICAL SPECIFICATION 1.2. 1 12- '

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/ PERMISSIBLE WEGION OF OPERATIOpN

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xN e 10_

i 6 N t-- o ,

x h~ NXPOSURi' (pWd/ST)

UN IT (kW /ft)lI cr O 0.00 i o '.6 5

c. s 1 oo 4 .;2..

5.00 MO 3

< 6.00 1 .tb 9.00 12.07 10.00 12.24 12.50 12.32 18:88 25.00 li:0 11.30 1

30.00 10.57 35.00 10.04

1. "" ' RSR 6

45.00 7.92

• 48.P9 5.91 l

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, 0 5 10 15 20 25 30 35 40 45 50

! AVERAGE PLANAR EXPOSURE (GWd/ST)

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• CP&L Nucitor Fusi Sectior. File: NF-2202.020 82C10 Core Operating Limits Report Pogo 10, Revision 0 Figure 6 FUEL TYPE GE10 D8HXB329-12GZ1-100M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE P(APLHGR) LIMIT LANAR EXPOSURE 14 THIS flGURE IS REFERREj0 TD BY 3.2.1 13 TECHNICAL S ECl{lCATIOb

/N

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12 e

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/ PERMISSIBLE REGION OF CPEf% Tic N

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f evenet ter i fu n' N\ l  :

IGWd/Sli)~ (i;W/ft) N t-

E 0.00 1 0.52 \

3 9

OJ20 1.00 lio.57 1;Gr74- \ -

$ 2J00 3J00 10.92 l

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- 1 1.17 J 4J00 1 1.35

% b.30 1 1.53 ,

8, ,r.ua 7J00 nn 1 1.90 8J00 12.12 9J00 1!2.37 (

.. 10 00 1GJ3  ! \

12.60 12.82 4 15.00 12.65 20.00 12.13 25.00 1 1.47 6

v nn i n 9n ,

45.00 8.63 )6 50.50 5.90 5 i , , , , , , ,,,,,,,,,,,,,

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

_- - +me- vr -we

CP&L Nuclear Fuel Section File: NF 2202.020 B2C10 Core Operating Limits Report Page 11 Revision 0 Figure 7 Flow - Dependent MAPUICR Limit, MAPUICR(F) 1.0 -

so U

3 gs +

'gg "

0.s - M *

.s s'

i E

N h 08 -

MAPLHGRfF).MAPFACp MAPLHGRSTD h MAPLHGRSTO = 5TANDARD MAPLHGR LIMITS 0.7 .

MAPFACptF). MINIMUM (1.0, ApWC /100 + Bri g WC = % RATED CORE FLOW e AND Ag 8p ARE FUEL TYPE DEPENDENT

@ CONSTANTS GIVEN BELOW:

k O.6 -

2 MAXIMUM CORE FLOW 1% retodi Ap Op 0.5 - 102.5 0.6784 0.4861 107.0 0.0758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 G.3828 0.4 ' I I I I I  !

30 40 50 60 70 80 90 100 110 CORE FLOW 1% rateot This figure is referred to by Technical Specification 3.2.1

4 CP&L Nuclear Fuel Section File: NF-2202.020 B2C10 Core Operating Limits Report Page 12, Revision 0 Figure 8 Power - Dependent MAPUICR Limit, MA?UICR(P) 10 1 09 -

N r .

$ 08 "-

U j M APLHGRIPl = MAPFACp

• M APiHGRSTD

[

<r 07 s 50% CORE FLOW MAPLHGASTD. STANDARD MAPLHGR LIMITS E

FOR 25% >P NO THERMAL LIMITS MONITORING 3 REQUIRED 5

FOR 25% sP<30%:

{y 0.6 -

MAPFACp= 0 585 + 0 005224 (P- 30%)

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

o I > 50% CORE FLOW FOR > 50% CORE FLOW

' O5 -

l g /

g af FOR 20% sP:

l M APFACp = 1.0 + 0.005224 (P- 100%)

1 0.4 I I I l I l I 20 25 30 40 50 60 70 80 90 100 POWER 1% rated)

This figure is referrei to by Technical Specification 3.2.1

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_ CP&L Nuclear Fuel Section File: NF 2202.020 B2010 Core Operating Limits Report Page 13 Revision 0 TABLE 1 MCPR LIMITS Non-Pressurization Transient MCPR - 1.25 (CE8X8NB 3, CE8X8NB, CE8XSEB, and BP8XBR fuel types)

Pressurization Transient MCPR MCPR Option A Fuel Tyne Exoosure Range CE8X8NB 3 CE8X8NB CE8X8EB BP8X8R BOC10 to EOC10 2000 MVd/ST 1.35 1.35 1.35 1.35 E0C10-2000 MVd/ST to EOC10 1.36 1.36 1.36 1.36 MCPR Option B Fuel Tyne Exoosure Rance ~ CE8X8NB 3 'CE8X8NB GE8X8EB BP8X8R BOC10 to EOC10 2000 mwd /ST 1.28 1.28 1.28 1,28 EOC10-2000 mwd /ST to EOC10 1.32 1.32 1.32 1,32 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2

2 + e. _ k aa--

CP6L Nuclear Fuel Section File: NF.2202.020 B2C10 Core Operating Limits Report Page 14, Revision 0 Figure 9 Flow - Dependent MCPR Limit, MCPR(F)

FOR We , RATED CORE FLOW) < 40%

MCPRtFi = ( ApW FOR WC (% AATED CORE FLOW) a 40%

C /100 + Brl MCPR(F) MAX (1.20, ApWC/100 + 0pl

,7 , 'll + 0.003 2 (40 - WC 'l VAX FLOW Ar Dr 117.0 -0.632' 1809 112.0 -0,602 1.747 1.6 -

107.0 - 0.586 1.697 102.5 - 0.571 1.655 1.5 -

M AXIMUM FLOW RATE = 117.0%

E

' 112.0 %

4 107.0 %

102.5%

14 -

1.3 -

1.2 -

g,j i i i f f i l i I 20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% ratect This figure is referred to by Technical Specification 3.2.2.1

CP&L Nuclear fuel Section File: NF 2202.020 B2C10 Core Operating Limits Report Page 15. Reivision 0 j Figure 10 l Power - Dependent MCPR Limit. MCPR(P)

/ ,

4 O QLMCPR

] -- -

A ATED MCPR MULTIPLIER ikp# -

I 2.3 -

(- ,,

l

. 50% CORE FLOW OPERATING LNIT MCPR (Pl.Kp' ODERATING LIMIT MCPR 11001

~

3

l FOR Pc 25% NO THERMAL LIMITS MONITORING REQUIRED I l l NO LIMITS SPECIFIED

'I ~

! l

$ FOR 25% s 9< PgypAgg ;PBYPASS = 30%I

I I Q go l Kp IKgyp + 0 02130% - Pil/OLMCPR (1001 r c 50% CORE FLOW

! KBYP 19 FOR s 50% CORF FLOW

's i9 = 2.2 FOR > 50% CORE FLOW l l g FOR 30% 5 Pc45%:

et 18 -

R Kp = 1 28 + 0 0134 (4 5% - Pt

s. /

4 1.5 x L. -- FOR 45% sPc60%:

2 l l Kp = 1.15,0 0086 7160% - Pt 1 1.4 -

l 5  !

FOR 60% s P.

e l l

} }3 l

l g Kp = 10 + 0 00375 (100% Pi

? 1 5 12 -

, l 1

-$ i i 1 2 1.1 -

l l l

-S l l I I

'd 1.0 I I ' I  ! I i

• ! i 20 25 30 40 50 60 70 80 90 100 PBYPASS POWER (% ratem This figure is referred to by Technical Specification 3.2.2.1

1 4 '

CP&L Nuclear Fuel Section File: NP 2202.020 B2C10 Core Operating Limits Report Page 16, Revision 0 TABLE 2 RBM SYSTEM SETPOINTS 5etroint Trio Setooint Allowable Valug Low Power Sotpoint (LPSP') 27.0 $ 29.0 Intermediate Power Setpoint (IPSP') 62.0 s 64.0 High Power Setpoint (HPSP') 82.0 $ 84.0 low Trip Setpoint (LTSP b) s 115.1 s 115.5 Intermediate Trip Setpoint (ITSPb) s 109.3 5 109.7 High Trip Setpoint (HTSPb) s 105.5 s 105.9 tea s 2.0 seconds s 2.0 seconds

• Setpoints in percent of Rated Thermal Power.

b "

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

$ 115.1/125.0 of full scale.

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