ML20246N741

Rev 1 to Brunswick Unit 2,Cycle 8 Core Operating Limits Rept,Mar 1989

ML20246N741
Person / Time
Site:	Brunswick
Issue date:	03/31/1989
From:	Clements T, Devoe M CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20246N740	List: ML20246N733 ML20246N741 ML20246N753
References
NUDOCS 8907200032
Download: ML20246N741 (10)

Text

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s r e. - ~B2C8 Core'Opzrating. Limits Report

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-BRUNSWICK UNIT 2, CYCLE 8

' CORE OPERATING LIMITS REPORT MARCH 1989 Controll'edCopy'01 Prepared By: M. J. DEV0E i.

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Approved By: 6. #.4'd.e'u) ,f/4 - ' ate. ,

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., Talmage Clements ,

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lCP&L Nuciaar'Fu21'Szction Files' NF-2202.013'

, ,' , ' B2C8'Cara Oparcting Limits Raport Paga.3, Revision 1 s -

INTRODUCTION AND

SUMMARY

[ . This report provides the values of the AVERACE PLANAR LINEAR HEAT l .CENERATION RATE (APLHCR).limite, the Kg core flow adjustment factor, . and the MINIMUM CRITICAL POWER RATIO (MCPR) limits for Brunswick Unit 2, Cycle 8 as required by Technical Specification 6.9.3.1.

Per: Technical Specifications.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.

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

APLHCR LIMITS '

The limiting APLHGR value for the most limiting laitice (excluding natural uranium) of each fuel type as a function of AVERACE PLANAR EXPOSURE is given in Figures 1,2,3, and 4. These values were determined with the SAFE /REFLOOD LOCA methodology described in CESTAR-II (Reference 2).

Figures 1,2,3, and 4 are used when hand calculations are required as specified in Technical Specification 3.2.1.

MCPR LIMITS The ODYN OPTION A, ODYN OPTION B, and non pressurization transient MCPR limits for use in Technical Specifications 3.2.3.1 and 3.2.3.2 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 critical power ratio correlation described in CESTAR-II.(Reference 2).

and are consistent with a Safety Limit MCPR of 1.04.

The Kg core flow adjustment factor for use in Technical Specification 3.2.3.1 is given in Figure 5.

REFERENCE (s)

1) CP&L Nuclear Fuel Section Quality Assurance File NF 2489.0014,

" Preparation of the Brunswick Unit 2, Cycle 8 Core Operating Limits Report", February 1989 (as supplemented). l

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

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CP&L ' Nucl: r Futi SIction -

B2C8. Core Operating Limits Report. . File: NF-2202.013

. Page 4, Revision 1 q

Figure 11 FUEL TfPE P8DRB265H (P8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR UMIT  !

VERSUS AVERAGE PL(ANAR EX)POSURE l 13 1 1.

l THIS FIGURE IS REFERRED TO BY ~

TECHNICAL SPECIFICATION'3.2.1 12,1 12,1 11 ,9 f x 11 ,9 11.6

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11.5 e \ 3.7 .

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Q PERIAISSIEILE REGION OF

\\ 94 OPEIMTION

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' i O 5 10 15 20 25 30 35 40 AVERAGE PLANAR EXPOSURE (GWD/ST)

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.. CP&L Nuclear Fuzi Srcti::n 82C8 Core Operating Lirnits Report File: NF-2202.013 Page 5, Revision 1

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Figure 2 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR LIMIT VERSUS AVERAGE PL(ANAR. EX)POSURE 13 i l

1 THIS FIGURE IS REFERRED TO BY l_

12.2 TECHNICAL SPECIFICATION 3.2.1 l 12.1 l

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11 it: [ PERMISSIBLE d$ 10.9 REC 10N OF g OPERATDN

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l 5 10 15 20 25 30 35 40 45  ;

AVERAGE PLANAR EXPOSURE (GWD/ST)

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. CP&L' Nucl:cr Fuel Section B2C8 Core Operating Limits Report File: NF-2202.013 Page 6 Revision 1.

Figure 3 FUEL TYPE BD317A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS' AVERAGE P APLHGR)POSURE NAR EX 13-

/ 12.85 5

j/ l 12.65

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12.07 i TECHNICAL SPECIFICATION 3.2.1 11.20 11 ,96

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OF ERATION 3 9 \

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5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWD/ST) o, ,

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t CP&L Nucidor Fud Saction File: NF-2202.013 B2CB- Core Operating Limits Report Page 7, Revision 1 Figure 4 FUEL TYPE BD323A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR LIMIT -

VERSUS AVERAGE PL(ANAR EX)POSURE '

1;2.62 l .

2,40 12, I2 /

THIS FIGURE IS REFERRED TO BY ~

'N l TECHNICAL SPECIFICATION 3.2.1

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,c 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWD/ST)

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• CP&L'Nucionr Fu21 S;ction File: NF-2202.013

,. 'B2C8 Cara Op;rcting Limits Rep;rt Pcg2 8, R2 vision 1 l

TABLE 1 MCPR LIMITS Fuel Type (s): P8X8R, BP8X8R, and CE8X8EB-Non-Pressurization Transient MCPR = 1.22 Pressurization Transient MCPR Exposure Range MCPR MCPR Option A Option B BOC8 to EOC8-2000 MWD /ST 1.29 1.22 EOC8-2000 MWD /ST to EOC8 1.30 1.26 THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATIONS 3.2.3.1 AND 3.2.3.2 I

CP&L Nucirr Fu!! S:ction ' File: NF-22o2.015 ETC8 Core Operating Limita Report Page 9, Revision .1 Figure 5 K, CORE FLOW ADJUSTMENT FACTOR 1.4 g l 1

l THIS FIGURE IS REFERRED TO BY l TECHNICAL SPECIFICATION 3.2.3.1-l 1.3 %

AUTOMATIC FLOW CONTROL N N N l

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MANUAL. FLOW CONTROL h h i

SCOOP TUBE SETPOINT CALIBRATION POSI110NED s SUCH THAT FLOW MAX . jg2,,g

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= 1' 2 as

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= 1' 70s 0.9

, 30 40 50 60 7o s'o g'o 100 i

CORE FLOW (5) I

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ENCIDSURE 2 CORE OPERATING LIMITS REPORT, REVISION 1, MARCH 1989 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2

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