Text

Rev 1 to Brunswick Unit 1,Cycle 7 Core Operating Limits Rept
	ML20247E577
Person / Time
Site:	Brunswick
Issue date:	03/03/1989
From:	Clements T; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20247B232	List: ML20247B227; ML20247B235; ML20247E577; ML20247E587;
References
	NUDOCS 8904030164
	Download: ML20247E577 (11)
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CP&L Nuclx r Fu21 SIctica ~Filei.NF-2202;014:

BlC7 Core Operating Limits Report- Page 1, Revision 1.

BRUNSWICK UNIT 1, CYCLE 7 CORE OPERATINC LIMITS REPORT MARCH 1989

' Controlled Copy Prepared By: M. J. DEVOE Approved By: I6 s//// A Date 3 t/tc/

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CP&L Nuclect Fu21'Sicticn ' Filet ~NF-2202.014'

- 81C7 Core.. Operating Limits Report- .;Page 2, Revision 1 t-s LIST OF EFFECTIVE PAGES o

Page(s) Revision L

1-10 1=

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CP&L Nuciscr Fu21 S2ction Files NF-2202.014

~B1C7 Core Operating' Limits _ Report Page 3, Revision l1-INTRODUCTION 'AND

SUMMARY

L

_ This report provides the values of. the AVERACE PLANAR LINEAR HEAT CENERATION RATE (APLHCR) limits, the Kg core flow adjustment-factor, cand the MINIMUM CRITICAL POWER RATIO (MCPR) limits for Brunswick Unit 1, Cycle 7.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.

i 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 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, 4, and 5. These values were determined with the SAFE /REFLOOD LOCA methodology described in CESTAR-II (Reference 2).

Figures 1,2,3, 4, and 5 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-PLUS critical powe. 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 6.

REFERENCE (s)

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1) CP&L Nuclear Fuel Section Quality Assurance File NF 2489.0016,

" Preparation of the Brunswick Unit 1, Cycle 7 Core Operating Limits Report", February 1989 (as supplemented . l

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

I i

I CP&L Nuclear Fuel Section File: NF-2202.014

- 81C7 Cora Operating Limits Report Page 4, Revision 1 Figure 1 FUEL TfPE P8DRB284H (P8X8R)

< AVERAGE PLANAR LINEAR HEAT i

GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE l l- l l l l l l THIS FIGURE IS REFERRED TO BY ~

TECHNICAL SPECIFICATION 3.2.1.

12,0 12,0 12 11 /~

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ll '1 11.2 PERMISSIBLE 6 REGION OF g OPE' RATION

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

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i CP&L' Nuclear Fuel Ssetion File: NF-2202.014 B1C7 Core Operating Umits Report. . Page 5, Revision 1 -

Figure 2 FUEL TYPE P8DRB299 (P8X8R AVERAGE PLANAR LINEAR HEAT)

GENERATION RATE APLHGR LIMIT VERSUS AVERAGE PL(ANAR EX)POSURE-13 THIS FICURE IS REFERRED TO BY ~

12,2 12,3 TECHNICAL SPECIFICATION 3.2.1 g #N 12,1 12 (

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j PEF!MISSIBLE w o 10.9 RE0lON OF OPIRATDN

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g4 3s ,

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

l CP&L Nuclear. Fuel Section File: NF-2202.014 3- B1C7 Coup : Operating Limits Report Page 6,-. Revision 1 Figure 3 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR UMIT-VERSUS AVERAGE PL(ANAR EX)"OSURE 13 THIS FIGURE IS REFERRED TO BY. -

12,2 12.3 . TECHNICAL SPECIFICATION 3.2.1

, #N 12.1 12

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N-11.C-

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1 CP&L Nuclear Fuel- Section - .

File:' NF-2202.014 B1C7 Cote- Operating Limits Report. Page 7. Revision 1 Figure 4 d AVERAGE PLANAR LIN(EAR HEATFUEL TYP GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE-14

~13,10

(- 12,75 THIS FIGURE IS REFERRED TO BY 13 _

TECHNICAL SPECIFICATION 3.2.1

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12 -- 7 t '

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v REGION OF OF ERAfiON 96 l--

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6.06 6 .

O 5 10 15 20 25 30 35 40 45 50 AVERAGE P!ANAR EXPOSURE (GWD/ST) ,

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l CP&L' Nuclear Fuel Section .

File: NF-2202.014 B1C7 Core Operating Limits Report Page 8, Revision .1 l

Figure 5 FUEL TYPE BD339A l

AVERAGE PLANAR LIN(EAR HEATGE8X8EB GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE 14 g3- 12.88 THIS FIGURE IS REFERRED TO BY _

\ q.59 H A A ON 3.2.1 N 12.08

,2 'iV N N 11 .58

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REGIOPl OF 10.3'6 OF ERAMON H (

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b a 9.58 s

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6.22 c 6

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

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.CP&L' Nuciccr Fuel S2cticn Fils: .NF-2202.014 B1C7 Core. Operating Limits Report Page 9, Revision 1 TABLE 1 MCPR LIMITS

-Fuel Type (s): P8X8R, BP8X8R, and GE8X8EB Non-Pressurization Transient MCPR = 1.25

-Pressurization Transient MCPR Exposure Range MCPR MCPR Option A' Option B BOC7 to EOC7-2000 MWD /ST 1.32 1.25 EOC7-2000 MWD /ST to EOC7- 1.34 1.30 THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATIONS 3.2.3.1 AND 3.2.3.2

i CP&L Nuclear Fuel Section File: NF-2202.014 -

81C7 Core Operating Umits Report Page 10, Revision 1 r

Figure 6 Kr CORE FLOW ADJUSTMENT FACTOR 1.4 l l l THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3.1

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1.3

'N AUTOMATIC FLOW CONTROL N

N 2

NN 1.1 s 3

MANUAL, FLOW CONTROL SCOOP TUBE SETFOINT \ i CAUBRATION POSIllONED SUCH THAT FLOW W = 102.5s 1*0 """

=1' 2.Os

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

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ENCIDSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT ELIMINATION OF CYCLE-SPECIFIC PARAMETER LIMITS (NRC GENERIC LETTER 88-16)

CORE OPERATING LIMITS REPORT - UNIT 2 I

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ML20247E577

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SUMMARY

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