ML20246A468

Rev 2 to Core Operating Limits Rept,Brunswick Unit 1,Cycle 7

ML20246A468
Person / Time
Site:	Brunswick
Issue date:	08/31/1989
From:	Supko E CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20246A457	List: ML20246A453 ML20246A468
References
NUDOCS 8908220469
Download: ML20246A468 (11)

Text

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CP&L Nucicer Fu21 S2ction File NF-2202.014

.B1,C7 Cora Optrating Limits Report Page 1, Revision 2 BRUNSWICK UNIT 1, CYCLE 7 CORE OPERATING LIMITS REPORT AUGUST 1989 CONTROLLED COPY A  ;

PREPARED BY: E. M. Supko

~ 7 APPROVED BY: ag/ DATE: 6 T. ~Clements Princ[ipalEngineer

/ /

Transient Analysis 1

8908220469 890818 PDR ADOCK0500g{5

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f-i CP&L Nuc1scr Fumi Ssetion File: NF-2202.014'

,, . Bl.C7 Cora Opsrcting Limits Report Page 2, Revision 2 p

' LIST OF EFFECTIVE PACES Page(s) Revision 1-2 2 3-8 1 9 2 10 1 Revision 0 - Original Core Operating Limats eleport.

Revision 1 - Incorporates format changes requested by the NRC.

Revision 2 - Incorporates UAT or SAT as the source of recirculation pump power.

CP&L Nuclect Fu21 Section File: NF-2202.014

,, .BIC7 Core optrsting Limits Report Pcge 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 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 valees 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 perforned 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 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 6.

REFERENCE (s)

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).

CP&L ' Nuciser Fusi Stelion .

i.

' File: NF-2202.014 B1C7 Core Operating Umits Report Page 4 Revision 1 Figure 1 FUEL TYPE P8DRB284H (P8X8R)

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

l l l' l l l -l l THIS FIGURE IS REFERRED TO BY -

TECHNICAL SPECIFICATION 3.2.1 12.0 12,0 12- o 11 . f-

,/ \,

11 ,1

'p '

11 .2 11.2 6-PERMISSIBLE REGION OF \

g a

OPEtRATidN

\s 10. 4 a

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g. h 9.8

^

\, 9,1 9

I 3 i 3 ll l i 0 5 10 15 20 25 30 35 40 45 l AVERAGE PLANAR EXPOSURE (GWD/ST)

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F

- CP&L Nuclear ~ Fuel Section . File: NF-2202.014 81C7 Core Operating Limits' Report Page 5, Revision 1 l

l Figure 2 FUEL TYPE P8DRB299 (P8X8R)

AVERAGE PLANAR. LINEAR HEAT E

GENERATION RATE APLHGR) LIMIT -

VERSUS AVERAGE PL(ANAR EXPOSURE 13 l

THIS FIGURE IS REFERRED TO.BY ~

g 12[3 TECHNICAL SPECIFICATION 3.2.1 g#N 12.1

,2 (

7 \

1.1.c

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e N 11- z N o 3: E PERMISSIBLE

-6 10,9 REGION lOF g OPI: RATION g K 10.,5 5

b

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9.0 8 ,

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

CP&L Naclear Fuel Section File: NF-2202.014 8107 Core Operating Umits Report Page 6 Revision 1 Figure 3 FUEL TYPE BP8DRD299 (BPBX8R)

AVERAGE PLANAR LINEAR HEAT  ::

GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE .,'

I3 '

l 8 l l l l l l ;l THIS FIGURE IS REFERRED TO BY i jf2 12.3 TECHNICAL SPECIFICATION 3.2.1  :

g/N 12.1 _

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l 11.C /

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2 N 11 3 [

]

PERMISSIBLE 6 10.9 REGION lOF g OPERATION

-5 J 10 s

g 10 -- \.5 g \- o N

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

~

.CP&L Nucler Fuel Section ' .

File. NF-2.202.014 -

1. - , B1C7: Core Operating Limits Report Page 7. Revision 1 l'

1 Figure 4 FUEL' TYPE BD3238 (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT -

GENERATION - RATE - APLHGR) LIMIT VERSUS AVERAGE- PL(ANAR EXPOSURE 14 13.10 l A 12.75 THIS FIGURE IS REFERRED TO BY I3 ^ _

TECHNICAL SPECIFICATT.ON 3.2.1 12 07

! 11 ,37 n

/1 41 11,29 h 10,66 v

' PERMn;SIBLE REGlott OF

\

OF ERAPON t-- N 9.96

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24 g u 9 x 52 8 \

7 6.06 6 ,

i i

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

1 4

CP&L Nuclear Fuel Section File: NF-2202.014 81C7 Core Operating Umits Report Page 8, Revision 1 i

Figure 5 FUEL TYPE BD339A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE 14 I

l 12.88 THIS FIGURE IS REFERRED TO BY i I3

\ .59

^ ^ " ' '

l N 12.08 12

/ M **

1.1 E h

.x v

PERM 13 SIB E REGION OF 10'36 OF'ERAn0N (

w K

58 s

3 g N \ 8379 e T 8

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6.22 <

6  ; g l , ,

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

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l:-. 4 iCP&L NdEIe,ar Fuil55$ctign L , File s ' .'NF-2202 L O 14.

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,  ;-Q "'?81C7 Core [Op3 rating ! Limits;Rsports

- Psgs 9,: Revision 2. '

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TABLE 1

.c... ,

HCPR LIMITS' t

~'

. ['aeE Tyne(s) -- P8X8R, BP8X8R, and CEBX8EB Non-Pressurization Transient' MCPl; = 1.25 ,

' Pressurization TransientJ MCPR

.MCPR HCPR

' Exposure Range >

Og ion A  : Option B'

' DOC 7.To EOC7-2000 MWD /3T 1.33 1.26

l0C7-2000

MWD /ST To EOC7 'l.34 1.30 7

THIS TABLE IS REFERRED..TO BY

. TECHNICAL . S SPECIFICATIONS 3.2.3.1 AND 3.2.3.2 J

J 6668ICA

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i ig

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CP&L. Nuclear Fuel. Section ~ . File: NF-2202.014 4

'81C7 Core Operating Limits Report - Paget 10, Revision 1 Figure 6 Kr CORE FLOW ADJUSTMENT FACTOR 1.4 l ~

l l l THIS FIGURE IS REFERRED TO BY l

TECHNICAL SPECIFICATION 3.2.3.1 1~3 - \ \

NN N AUTOMATIC FLOW CONTROL 12

\ \

2 1.1 x

MANUAL FLOW col 4 TROL SCOOP TUBE ~ SETHOINT i CAUBRATION POSITtONED SUCH THAT FLOW MAX = 102.5s 1*O " '87 *

= 1' 2.Os

\ '

=1' 7.Os ,

~

0.9 n 30 _ 40 50 60 70 80 90 100 CORE FLOW (z) u

__1___..