ML20012A429

Rev 0 to Brunswick Unit 2,Cycle 9,Core Operating Limits Rept.

ML20012A429
Person / Time
Site:	Brunswick
Issue date:	02/19/1990
From:	Devoe M, Karcher K CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20012A428	List: ML20012A427 ML20012A429
References
NUDOCS 9003090519
Download: ML20012A429 (15)

Text

__. _ . _ _ _ _ _ _ _ .

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'CP&L Nuclear Fuel Section File: NF 2202.016 B2C9 Core Operating Limits Report Page 1 Revision 0 BRUNSWICK UNIT 2, CYCLE 9 CORE OPERATINC LIMITS REPORT FEBRUARY 1990 Controlled Copy 1 O

Prepared By: M. J. DeVoe i

Approved By:

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CP&L Nuclear Fuel Section File: NF-2202.016 q

B2C9 Core Operating Limits Report Page 3, Revision 0-INTRODUCTION AND

SUMMARY

This report provides the values of the power distribution limits and control rod withdrawal- block instrumentation setpoints for Brunswick Unit 2, Cycle 9 as required by Technical Specification 6.9.3.1. The values of the AVERAGE PLANAR.

LINEAR llEAT GENERATION RATE (APLHCR) limits, along with associated core flow and core power adjustment factors are provided as required by Technical Specification 6.9.3.1.a. The values of the MINIMUM CRITICAL POWER RATIO (MCPR) limits, along with associated core flow and core power adjustment factors are j provided as required by Technical Specifications 6.9.3.1.b and 6.9.3.1.c. The i control rod block upscale trip setpoints and allowable values are provided as l required by Technical Specification 6.9.3.1.d. l l

1 Per Technical Specifications 6.9.3.2 and 6.9.3.3, these values have been j determined using NRC approved methodology ano are established such .that all l 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 as is documented in Reference 1.

j, }

APUlGR LIMITS The limiting APDIGR value for the most limiting lattico (excluding natural

-uranium) of each fuel type as a function of planar average exposure is given in Figures 1,2,3,4, and 5 These values were determined with the SAFER /GESTR LOCA l

' methodology described in GESTAR-II (Reference.2). Figures 1,2,3,4, and 5 are j used when hand calculations are required as specified in Technical Specification 3.2.1.

The core flow and core power adjustment factors for use in Technical l Specification 3.2.1 are presented in Figures 6 and 7. For any given flow / power state the minimum of MAPLHGR(F) determined from Figure 6 and MAPLHCR(P) i determined from Figure 7 is used to determine the governing limit.  !

I i

l l

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CP&L Nuclear Fuel Section File: NF-2202.016

,3 B2C9~ Core Operating Limits Report Page 4, Revision 0-

_f MCPR LIMITS The ODYN OPTION A. ODYN OPTION B, and non pressurization transient MCPR-limits for use in Technical Specifications 3.2.2.1 and 3.2.2. 2 for each fuel' type as a function of cycle average exposure are given in Table 1. These values were determined with the GEMINI methodoloSy and GEXL PLUS critical power ratio corre-lation described in GESTAR II (Reference 2) and are consistent with the Safety Limit MCPR of 1.06 specified by Technical Specification 2.1.2.

The core flow and core power adj ustment - factors for use in Technical-Specification 3.2.2.1 are presented in Figures 8 and 9. For any given flow / power state the maximum of MCPR(F) determined from Figure 8 and MCPR(P) determined from ,

_ Figure 9 is.used to determine'the governing limit.  :

l ROD BLOCK INSTRUMENTATION SETPOINTS The nominal trip setpoints and allowable values of the control rod withdrawal '

. block instrumentation for use in Technical Specification 3.3.4 (Table 3.3.4 2) '

are presented in Table 2. These values were determined consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI methodology and GEXL-PLUS critical power ratio correlation described in CESTAR II l,_') (Reference 2).

x- '

REFERENCE (s)

1) CP&L Nuclear Fuel Section Quality Assurance File NF 2490.0004,

" Brunswick Unit 2, Cycle 9 Core Operating Limits Report",

February 1990.

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

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- CP&L Nuclear Fuel Section File: NF-2202.016 B2C9 Core Operating Umits Report Page 5 Revision 0 p

Figure 1 FUEL TYPE BP8DRB299 (BP8X8R)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE 13 THIS 11GURE IS REFERRED TC' BY TECHNICAL SPECIFICATIOb 3.2.1 12,2 -

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$('j)1-f Figure 2 '

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FUEL TYPE BD317A AVERAGE PLANAR LIN(EAR HEATGEBX8EB)

GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR EXPOSURE  ;

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CP&L- Nuclear Fuel Section: File: NF-2202.016 .

4./ -

B2C9 Core Operating Umits Report

- Page 7. Revision 0 r [,

Figure 3 .

I FUEL TYPE BD323A (GE8X8EB)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT '.

VERSUS AVERAGE PL(ANAR EXPOSURE 14-THIS FIGL RE SREFEFl RED TO BY 3.14 TECHNICA SF ECIFICAT ON 3.2. I

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File: tlF-2202.016'

~ 82C9 Core Operating Limits Report . Page 8,' Revision 0

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File: NF-2202.016 -

B209 Core Operating Umits Report. Poge 9. Revision O'

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CP&L Nuclear Fuel.Seetion .

' File: NF;2202.016 ,

,  ; B209-Core Operating. Limits. Report Page 10, Revision 0 Figuro 6 6

. Flow - Dependent MAPillGR Limit, MAPL 11GR(F)

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MAPLHGRSTD = STANDARD MAPLHGR LIMITS

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MAPFACp(F)= MINIMUM (1.0, ApWC1100 + BF)"

W C= % RATED CORE FLOW  ;

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- Ei MAXIMUM CORE FLOW -

(% rated) Ap. BF

- 102.5 0.6784 0.4861  !

0.5 -

107.0 0.6758- 0.4574 ,

112.0 0.6807 0.4214 117.0 0.6886. 0.3828

- 0.4 I I I I I I I' 30 40 50 60 70 80 90 100 110 CORE FLOW (% rated)

K1:

This figure is referred to by Technical Specification 3.2.1

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L 7y: :B2C9 Core Operating' Limits Report Page 11, Revision 0 7( Pr

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be' Figure 7; Power - Dependent'MAPulGR Limit, MAPulGP.(P) 1 g.

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• ri l :- g'O7 s 50% CORE FLOW MAPLHGRSTD = STANDARD MAPLHGR LIMITS i .- 4 y 1; 3 FOR 25% > P: NO THERMAL LIMITS MONITORING t

' 's O E REQUIRED LM l

g FOR 25% sP<30%

 : y . 0.6 .i w ~ MAPFACp = 0.5bb + 0.005224 (P- 30%) -

O FOR 5 50% CORE FLOW

c:

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> 50% CORE FLOW FOR > 50% CORE FLOW

g. e FOR 30% s P

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, l MAPFACp = 1.0 + 0.005224 (P- 100%)

1 0.4 I  ! I  !  !  !  !

20 25 30 40 50 60 70 80 90- 100-S- POWER (% rated)

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This figure is referred to by Technical Specification 3.2.1 O

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CP&1l Nticlear, Fuel Section. File:' NF-'2202. 016

=- : cl . j. . B2C9 Core-operating Limits Report Page':12,' Revision 0

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1. TABLE'1' MCPR LIMITS li Y , e Non-Pressurization Transient MCPR - 1.19 l(GE8X8NB, GE8X8EB, and BP8X8R fuel types)

-(

? Pressurization Transient MCPR 4

MCPR MCPR 1 Option A Option B i Fuel Tvoe Fuel Tvoe Exoosure Rance GEBX8NB . GE8X8EB' Eff.XfE GEDX8NB GE8X8EB LP8X8R: i BOC9-to EOC9-2000 MWD /ST- 1.32 1.31 1.31 1.25 1.24 1.24-

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. ..EOC9-2000 MWD /ST to.E009 1.33 1.32- 1.32 1.29 1.28. 1.28 I-This' table is referred to by ,

Technica1' Specifications  :

3.2.2.1 and 3.2.2.2 j.

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CP&L Nuclear Fuel-Section File: NF 2202.016

-mg. . B2C9 Core _ Operating' Limits Report Page'13, Revision 0

' 'qJ Figure 8 Flow - Dependent MCPR Limit, MCPR(F)

FOR WC (% RATED CORE FLOWi <40% FOR WC (% RATED CORE FLOW) a 40%

MCPR(Fl=(ApWC /100+ Bpl MCPR(F)= MAX (1.20, ApWC /100 + BF) -

, 'l1 + 0.0032 (40- Well 117.0 -0.632 1.809' 112.0 - 0.602 1.747 1.6 - 107.0 - 0.586 1.697  :(

102.5 - 0.571 1.655 ,

i 1.5 - MAXIMUM FLOW RATE = 117.0%

C- 112.0 % >

[ 107.0%

g 102.5%

1.4 -

O 1.3 -

1.2 -

I I I I I I I I I '

1.1

-20 30 40 50 60 70 80 90 100 110 120 CORE FLOW (% rated)

This figure is referred to by Technical Specification 3.2.2.1 1

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CP&L Nuclear Fuel Section File: NF 2202.016

, 9- lB2C9 Core Operating Limits Report: Page 14 Revision 0 N.).

• 3 Figure 9 Power - Dependent MCPR Limit, MCPR(P) ,

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k 0: RATED MCPR MULTIPLIER (Kp) r '

Z l I w 2.3 -

e OPERATING LIMIT MCPR (P).Kp' OPERATING LIMIT MCPR (100)

" I

> 50% CORE FLOW

@ 2.2 l FOR P<25%: NO THERMAL LIMITS MONITORING REQUIRED e i -l l NO LIMITS SPECIFIED p 21 ~

FOR 25% s P<PBYPASS: (PSYPASS = 30%)

i i e ,

l. Kp = lKgyp + 0.02 (30% - P)l/OLMCPR (100) y-2.0 -

[

j .-  ! g s 50% CORE FLOW KBYP= 1.9 FOR s 50% CORE FLOW

=

3,9 _ l = 2.2 FOR > 50% CORE FLOW .;

• l l FOR 30% sP<45%:

I'0 ~' .

Kp = 1.2 B + 0.0134 (4 5% - P)

O 2 # '

a. 3,$"_ FOR 45% sP<60%:

'/ ):

3

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@. l g Kp= 1,15 + 0.00867 (60% -P)

~

. h I'#  ! l FOR 60% sP:

i 1- l W 1.3 --

l- g Kp = 1.0 + 0.0037 5 (100% - P) i e

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=8- 1. I I I E j,o l I t i l i I I i

• 40 50 60 70 80 90 20 -25 30 100 PBYPASS POWER (% rated)

This figure is referred to by Technical Specification 3.2.2.1 G

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CP&C Nuclear; Fuel Sestion- File: 'NF-2202.016.

-; " 'l

.B2C9 Core Operating Limits Report Page 15, Revision 0 r, r q '?

TABLE 2 RBM SYSTEM SETPOINTS Setooint- Trio Setooint Allowable Value Low Power Setpoint (LPSP') $ 27,0. 5 29,0 Intermediate Power Setpoint (IPSP*) $ 62,0 $ 64.0 High Power Setpoint (HPSP*) $ 82,0 s 84,0 Low Trip Setpoint -(LTSPb) s 115,1 s 115',5 Intermediate Trip Setpoint (ITSP b) s 109.3 $ 109.7 High Trip Setpoint (HTSP b) $ 105.5 s 105,9 td2 5 2.0 seconds s 2.0 seconds O

• Setpoints in percent of. Rated Thermal Power.

b Setpoints relative to a full scale reading of 125, ,For example, s 115,1 means s 115.1/125.0 of full scale.

This table is referred to by Technical Specification 3.3.4 (Table 3.3.4-2)

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