ML20235T402

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Cycle 8,Core Operating Limits Rept,Feb 1989
ML20235T402
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 02/15/1989
From: Clements T, Devoe M
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20235Q839 List:
References
NUDOCS 8903080267
Download: ML20235T402 (9)


Text

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.CP&L.'Nuciscr Fu:1 Sicticn Filot. NF-2202.013

'B2C8., Core Operating;' Limits Report- _Page 1, Revision 0 h,

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BRUNSWICK UNIT 2,- CYCLE 8

' CORE OPERATING LIMITS REPORT-FEBRUARY 1989 Controlled Copy n

Prepared By: M. J. DEV0E o

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Approved By: / 2a e > Date (#

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Talmage Clements Principal Engineer Transient Analysis 8903000267 890220 PDR ADOCK 05000324 i P PDR

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CP&L Nuclocr Fual S2cticn Fils: NF-2202.013 B2C8 Core Operating Limits Report Page 3, Revision 0 INTRODUCTION AND

SUMMARY

j This report provides the values of the AVERACE PLANAR LINEAR HEAT GENERATION 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.

l- Per Technical Specifications 6.9.3.2 and 6.9.3.3, these values have been I

determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysia are met. '

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

APLHCR LIMITS The limiting APLHCR value for the most limiting lattice (excluding j 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). l Figures 1,2,3, and 4 are used when hand calculations are required as specified in Technical Specification 3.2.1.

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MCPR LIMITS 1 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.

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

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CP&L Nuclear Fuel Section File: NF-2202.013 B2C8. Core Operating Limits Report Page 4, . Revision 0 1

Figure 1 FUEL TYPE P8DRB265H (P8X8R)

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

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'CP&C Nucieor Fuel Section L B2C8--Core Operating Limits Report : File: NF--2202.013 .

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J FUEL TYPE BP8DRB299 :(BP8X8R)- ]

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CP&L Nuclear Fuel Section- File: NF-2202.013 82C8 Core Operating Limits Report Page 6, Revision 0 Figure 3 FUEL TYPE BD317A (GE8X8EB)

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GENERATION RATE ' APLHGR LIMIT VERSUS AVERAGE PL(ANAR EX)POSURE 13 1 2.85 12-

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-l CP&L Nuclear Fuel Section: File: NF-2202.013 82C8 Core Operating Umits Report Page .7, Revision 0 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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pL , e, CP&L Nuciccr.Fu21 Ssetion Filot: .NF-2202.013 B2C8. Core Operating Limits, Report Page-8, Revision 0 TABLE 1-MCPR LIMITS Fuel Type (s): P8X8R, BP8X8R, and CE8X8EB Non-Pressurization Transient MCPR = 1'22 .

Pressurization Transient MCPR r

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 i

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CP&L 'N'uclear Fuel Section File: NF-2202.013 k;';

  • 182C8 Core Operating: Limits Report Page 9,~ Revision 0 r

Figure 5

,. K, CORE FLOW ADJUSTMENT FACTOR l

1.4 1.3 '

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x MANUAL. FLOW Col 4 TROL 1 SCOOP TUBE SETFOINT CALIBRATION POSITIONED SUCH THAT FLOW MAX = 10 1.0

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

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