ML20247E587

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

ML20247E587
Person / Time
Site:	Brunswick
Issue date:	03/02/1989
From:	Clements T CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20247B232	List: ML20247B227 ML20247B235 ML20247E577 ML20247E587
References
NUDOCS 8904030174
Download: ML20247E587 (9)

Text

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! CP&L Nuclocr Fu21 S:ctica Fil'stL NF-2202.013 L B2C8 Core Operating Limits Report:

- Page 1, Revision 1 i;

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BRUNSWICK UNIT 2, CYCLE'8 CORE OPERATING LIMITS REPORT MARCH 1989 Controlled Copy Prepared By: M. J. DEV0E Approved By: 6 4thf , ,/4 e ate l f t/

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Talmage Clements Principal Engineer Transient Analysis '

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- CP&L Nuciser Fu21:$1ction . Files NF-2202.013 2

' B2C8 Core Operating. Limits Report: Page 2, Revision 1 LIST OF EFFECTIVE PAGES.

.Page(s) Revision 1-9 1

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-CP&L Nucider Fu21 S;ctien Fils: NF-2202.013 B2C8 Core Operating Limits Report Page 3, Revision 1 INTRODUCTION AND

SUMMARY

This report provides the values of the AVERACE PLANAR LINEAR HEAT CENERATION RATE (APLHCR) limits, 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.

i APLHCR LIMITS i

The limiting APLHCR value for the most limiting lattice (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 IDCA 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, "Ceneral Electric Standard Application for .l Reactor Fuel" (latest approved version). I

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5 CP&L Nucieor Fuel Section .

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File: NF-2202.013 1 82C8 Core _ Operating Limits Report' Page 4, Revision 1 -

1 Figure 1 FUEL TYPE' P8DRB265H (P8X8R)

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

THIS FIGURE IS REFERRED'TO BY ~

TECHNICAL SPECIFICATION 3.2.1 12.1 12,1 11 .9 f x 11 ,9

12. g

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11.6 11.5

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2 N 0.1 SJ 10 PERIAISSIBLE \\ 9*4 Q REGION OF q

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. j 0 5 10 15 20 25 30 35 40 AVERAGE PLANAR EXPOSURE (GWD/ST)

CP&L-Nuclear Fuel Section File: NF-2202.013 I B2C8 Core _ Operating Limits Report , Page 5, Revision 1 '

Figure 2 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE 13 l

l THIS FIGURE IS REFERRED TO BY -

12,2 TECHNICAL SPECIFICATION 3.2.1 12

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s, z N:o E PEFtMISSIBLE 6 10.9 REGION OF g -

OPI: RATION

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

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CP&L Nuclear Fuel Section' File: NF-2202.013 -

G2C8 - Cora ' Operating Umits Report Page 6, Revision 1 Figure 3 -

FUEL TfPE BD317A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT .

GENERATION RATE ' APLHGR) LIMIT VERSUS AVERAGE' PL(ANAR EXPOSURE 13 .

I 2.85 g_ i / 1 12.65

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\ TECHNICAL SPECIFICATION 3.2.1 11.20 11 ,96 h

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5.91 5' m , ,

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

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CP&L' Nuclear Fuel Section Fi(e: NF-2202.013

. 82C8 Cote Operating Limits Report Page 7, Revision l' Figure 4 FUEL TYPE BD323A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE. APLHGR LIMIT VERSUS AVERAGE PL(ANAR EX)POSURE 1 2.62

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[12.40 12.72 12- /

c. THIS FIGURE IS REFERRED TO B

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TECHNICAL SPECIFICATION 3.2.1 12,04

, 11 .33 11 1 1.30

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$ 10.11 v REGION OF OPERAnON 3 9 \

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

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CP&L'N'uciscr'Fust s Ssetien Files NF-2202.013 j f' -

f82C8 Core Operating Limits Report '

'Page 8, Revision'1'

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TABLE 1=

MCPR LIMITS-Fuel-Type (s):~ P8X8R,' BP8X8R, a'nd CE8X8EB 3..

r lNon-Pressurization Transient MCPR = 1.22 1

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 u.

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CP&L Nuclear Fuel Section File: NF-2202.013 B2C8. Cots Operating Limits Report j Page 9, Revision 1 l

Figure 5 )

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1 K, CORE FLOW ADJUSTMENT FACTOR 1.4 l

THIS FICURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3.1

'1 13 '

AUTOMATIC FLOW CONTROL

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N MANUAL. FLOW COlRROL SCOOP TUBE SETFOINT CAUBRATION POSn10NED SUCH THAT FLOW MAX = 102.5s 1.0 " '"7* '

=1' 2.Os

=1' 7.Os 0.9 30 40 50 60 70 80 90 100 CORE FLOW (z)

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