ML20101B624

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Cycle 12 Core Operating Limits Rept
ML20101B624
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 02/01/1996
From: Siphers J, Thomas R
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19355C768 List:
References
NF-2495.0083, NF-2495.0083-R, NF-2495.0083-R00, NUDOCS 9603140397
Download: ML20101B624 (19)
v • d • e


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CP&L Nuclear Puels Mgmt & Safety Analysis Fde: NF-2495.0083 i B2Cl2 Core Operating Limits Report Page 1, Revision 0 i

o BRUNSWICK UNIT 2, CYCLE 12 CORE OPERATING LIMITS REPORT FEBRUARY 1996 d

i 4

Prepared By: ,d.

[ Roger L. 'Ihop(as, Jr.

I Approved By:hktu - M ate: 2 !/ 0 John T. Siphers Acting Supervisor BWR Fuel Analysis KTONTROL\DOCUMENITB2C12COLREOLRB212.WPD 9603140397 960304 PDR ADOCK 05000324 P PDR

4 CP&L Nuclear Puels Mgmt & Safety Analysis File: NF-2495.0083 B2Cl2 Core Operating Limits Report Page 2. Revision 0 LIST OF EFFECTIVE PAGES

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CP&L Nuclear Puels Mgmt & Safety Analysis File: NF-2495.0083 B2Cl2 Core Operating Limits Report Page 3, Revision 0 INTRODUCTION AND

SUMMARY

nis report provides the values of the power distribution hmits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2 Cycle 12 as required by Technical Specification 6.93.1. De values of the Average Planar Linear Heat Generation Rate (APLHGR) limits, along with associated core flow and core power adjustment factors are provided as required by Technical Specification 6.93.1.a. De values of the Minimum Critical Power Ratio (MCPR) 1imits, along with associated core flow and core power adjustment factors are provided as required by Technical Specifications 6.93.1.b and 6.93.1.c. He control rod block upscale trip setpoints and allowable values are provided as requi.ed by Technical Specification 6.93.1.d.

1 Per Technical Specifications 6.93.2 and 6.933, these values have been determined using NRC-approved methodology j 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 Fuels Management & Safety Analysis (NFM&SA) Quality Assurance requirements as documented in Reference 1. l l

APLHGR LIMITS De limiting APLHOR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of ,

planar average exposure is given in Figures 1 through 8. These values were deternuned with the SAFER /GESTR LOCA methodology described in GESTAR-II (Reference 2). Figures I through 8 are to be used when hand calculations are l required as specified in Technical Specification 3.2.1.  !

l The core flow and core power adjustment factors for use in Technical Specification 3.2.1 are presented in Figures 9 and 10. For any given flow / power state, the sninimum of MAPLHOR(F) determined from Figure 9 and MAPLHOR(P) determmed from Figure 10 is used to determine the governing limit.

MCPR LIMITS He ODYN OFTION 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. Rese values were determined with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-II (Reference 2) and are consistent with the Safety Limit MCPR of 1.09 specified by Technical Specification 2.1.2. De analysis was performed without End of Cycle-Recirculation Pump Trip (EOC-RPT) operable.

De core flow and core power adjustment factors for use in Technical Specification 3.2.2.1 are presented in Figures 11 and 12. For any given flow / power state, the maximum of MCPR(F) deternuned from Figure 11 and MCPR(P) determined from Figure 12 is used to determine the governing limit.

KTONTROL\DOCUMDrI\B2C12COLRCOLRB212.WPD

CP&L Nuclear Puels Mgrnt & Safety Analysis Rie: NF-2495.0083 B2C12 Core Operating Limits Report Page 4, Revision 0 ROD BLOCK INSTRUMENTATION SETPOINTS Re 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. Rese 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 correlation described in GESTAR-II (Reference 2).

REFERENCE (s)

1) CP&L Nuclear Puels Management & Safety Analysis Design Activity 95-0083;" Preparation of the Brunswick Unit 2, Cycle 12 (B2C12) Core Operat mg Limits Report (COLR), Revision 0;" February i

19%; NF-2495-0083.

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

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.. l CP&L Nuclear Fuels Mgmt & Sofety Anolysis Flie: NF-2495.0083 B2C12 Core Operating Limits Report Poge 5, Revision 0 Figure 1 FUEL TYPE NBD330A (GE8X8NB AVERAGE PLANAR UNEAR HEAT )

GENERATION RATE APLHGR) UMIT VERSUS AVERAGE PL(ANAR EXPOSURE 13

  • 4N .AL $b 3 .1 i2 r xs
/

7 P DthIISS BU F R EGION 3F

" / U NUW k'

/ N N

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E ME (E7tt) \

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5.51 11 40 9 E.61 11 56 9.92 12 07 11 .02 12 24 1J.78 12 32 7  ;-.53 ;2 ;;

22.05 11 63 k 27.56 11 10 33.07 10 57 U'M '!N (\

49.60 7 Si

  • 54.00 5 91 5

0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

CP&L Nuclear Fuels Mgmt & Safety Anolysis File: NF-2495.0083 B2C12 Cors Operating Um'ts Report Page 6. Revision 0 Figure 2 FUEL TYPE NBD329A (GE8X8NB AVERAGE PLANAR UNEAR HEAT )

GENERATION RATE APLHGR) UMIT VERSUS AVERAGE PL(ANAR EXPOSURE 13 ~~

'rHl! FOUFEt intr e.ca:u10Irr b% '

REC 4NNA SP [CWICAD 3.2.1 12 -

N FEPaucca e \

/ FEGM 6F \

11 f

f CMADM \ 3 if \

N N*

2 10 N \

a \

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8 0, 4.41 11 48 1 4 5.51 11 63 11 .02 12.56 13.78 12.44 18,53 12 18

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33,07 10,58 38,58 10,05 N an !N

  • 54 '22 5 96 5

0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

f .

CP&L Nuclear Fuels Mgmt & Sofety Anolysis File: NF-2495.0083 82C12 Core Operating Umits Report Poge 7. Revision 0 Rgure 3 FUEL TYPE GE10-P8HXB329-12GZ1-100M-150-T (GE8X8NB-3)

AVERAGE Pt.ANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 T #S FIGJRE IS in. r.nu.0 TC B1 '

T :CH WCL!PEOFICATDN 3.2,1 13 A

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9.92 12 37 7

1 .02 12 83 \

'J.75 12,52 18.53 12 65 22.05 12 13 27.56 11.47 6

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49.60 8 63

  • 55.67 5 90 5 ,

0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

CPM Nxlear Fuels Mgmt & Sofety Anolysis Flie: NF-2495.0083 B2C12 Core Operating Limits Report Page 8. Revision 0 Figure 4 FUEL TYPE GE10-PBHXB324-12GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 EIIS FIGJRE IS Rt. t.nu.u TC BY E:CH WICJL!iPECIFil:ATIM4 3.2.1 13

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44.09 9 52 49.60 8 78 3 55,12 6 27 6

0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

- .. . ... . . ~ _ . - . . - -. . . - _ _ . . - . - . _ _ _ - . - . - . - _ . . _ - - - _ _ _ _ . _ _ _ _ - _ _ _

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CP&L Nuclear Fuels Mgmt & Sofety Anolysis File: NF-2495.0083 B2C12 Core Operating Umits Report Page 9, Revision 0 4

Figure 5 1

FUEL TYPE GE10-P8HXB320-11GZ-100M-150-T (GE8X8NB-3)

. AVERAGE PLANAR UNEAR HEAT 1

GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 1

14

EUS FIGJRE IS nr. r.nnu TC BP
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CHWICJLliPECIFICATI'N4 3.2,1 13 1

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$ 5.51 8.61 11 11 53 68 7.72 11 84 E.82 1200 g a no so in 11 .02 12 33 1J.78 12 52 18.53 12 40 22.05 11 93 L 7

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0 5 10 15 20 25 30 35 40 45 50 55 60 3 AVERAGE PLANAR EXPOSURE (GWd/MT)

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l CP&L Nucleor Fuels Wgmt & Sofety Anolysis File: NF-2495.0083 B2C12 Core Operating Umits Report Page 10. Revision 0 Figure 6 FUEL TYPE GE10-P8HXB322-11GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 j V9S FIOJRE IS Rt. t.nC TC BP E:CHWICJLHPEdFitlATI'N4 3.2,1 13 A

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x.u i iuvo 38.58 10 26 44.09 9 52 49.60 8 78 3 55.12 6 29 6

0 5 10 15 20 25 30 35 40 45 50 55 60 l AVERAGE PLANAR EXPOSURE (GWd/MT) l l

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CP&L Nuclear Fuels Mgmt & Safety Anolysis File: NF-2495.0083 B2C12 Core Operating umits Report Page 11 Revision 0 Figure 7 FUEL TYPE GE13-P9DTB363-11GZ1-100T-146-T (GE13)

AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 TMSIMIJRE, 15 nr.r anntu TO ErP TECHPOL iPIClfICATiON;5.2 1 l 13 r+ %

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0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

CP&L Nuclear Fuels Wgmt & Sofety Anoivois

  • File: NF-2495.0083 82C12 Core Operating Umits Report Page 12, Revision 0 Figure 8 FUEL TYPE GE13-P9DTB363-11GZ-100T-146T (GE13)

AVERAGE Pl.ANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 --

THSl'IGljRE: !! ntrenntu TO BF TEMCL:iPICifICAT101;5.2, 1 13 D  %

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0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

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CP&L Nuclear Fuels Mgmt & Safety Analysis Fde: NF-2495.0083 B2Cl2 Core Operating Limits Report Page 13. Revision 0 Figure 9 Flow - Dependent MAPLHGR Limit, MAPLHGR (F) 1.0 -

  1. s o'%*

t%# *$g4*

0.9 -

+g sN e

0.8 -

,,, MAPLHGR(F)=MAPFACp MAPLHGRSTO MAPLHGASTD = STAN0ARD MAPLHGR UMITS I MAPFACp(Fl= MINIMUM (1.0, ApWC /100 + Spl OJ W C= % RATED CORE FLOW u.

0.6 a MAXIMUM CORE FLOW

(% ratedl Ap BF 0.5 -

102.5 0.6784 0.4841 107.0 0.6758 0.4574 112.0 0.8807 0.4214 117.0 0.8886 0.3820 0.4 I I I I I I I 30 40 50 to 70 SO 90 100 110 CORE FLOW (% ratedl

'Ihis figure is referred to by Technical Specification 3.2.1 K:EONTROL\DOCUMDmB2Cl2COLRTOLRB212.WPD

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2495.0083 B2Cl2 Core Operating Limits Report Page 14 Revision 0 Figure 10 Power - Dependent MAPLHGR Limit, MAPLHGR (P) 1.0 t, 0.9 Y

I a

8 0.8 -

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MAPLHGR(Pl= MAPFACp'MAPLHGRgro 0.7 s 50% CORE FLOW MAPLHGASTD = STANDARD MAPLHGR UMITS fz FOR 25% >P: NO THERMAL UMITS MONITORING REQUIRED 0.6 - , FOR 25% s P< 30%:

g MAPFACp = 0.585 + 0.005224 (P- 30%)

g FOR s 50% CORE FLOW

  • 3 MAPFACp = 0.433 + 0.005224 (P- 30%)

f 0 .5 -

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> 50% CORE FLOW FOR > 50% CORE FLOW g e FOR 30%sP:

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

1

. 0.4 I I I I I I I

, 20 25 30 40 50 60 70 80 90 100 POWER (% rated) i l

This figureis referred to by Technical Specification 3.2.1 i

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CP&L Nuclear Puels Mgmt & Safety Analysis File: NF-2495.0083 B2C12 Core Operating Limits Report Page 15, Revision 0 l Table 1 MCPR Limits (EOC-RPT Not Required)

Non-pressurization Transient MCPR Limits FuelType MCPR Limit Exposure Range GE8x8NB-3/GE8x8NB GE10-P8HXB324-120Z-70M-150T 133 BOC12-EOC12 AllOthers 1.25 BOC12-EOC12 GE13 1.25 BOC12-EOCl2 Pressurization Transient MCPR Limits MCPR Opdon A Fuel Type MCPR Limit Exposure Range GE8x8NB-3/GE8x8NB 134 BOC12 to EOC12-2000 mwd /MT GE13 1.41 BOC12 to EOC12-2000 mwd /MT hhhh?Y'Y k khh ken % h GE8x8NB-3/GE8x8NB 134 EOC12-2000 mwd /MT to EOC12 GE13 1.48 EOC12-2000 mwd /MT to EOC12 MCPR Opdon B FuelType MCPR Limit Exposure Range GE8x8NB 3/GE8x8NB 1.27 BOCl2 to EOC12-2000 mwd /MT GE13 136 BOC12 to EOC12-2000 mwd /MT

{l%{l ~/b;& .[ ':4 f)j';,}lj'jy(Q,Yllljgf L' ll .

GE8x8NB-3/GE8xBNB 130 EOC12-2000 mwd /MT to EOCl2 GE13 1.40 EOC12-2000 mwd /MT to EOC12 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2 K: CONTROL \DOCUMDmB2C12COLRCOLRB212.WPD

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2495.0083 B2Cl2 Core Operating Limits Report Page 16, Revision 0 Figure 11 Flow - Dependent MCPR Limit, MCPR (F)

FOR WC (% RATED CORE FLOW) < 40% FOR WC (% RATED CORE FLOW) a40%

i MCPR(Flu (ApWc/100 + sp) MCPR(Fl= MAX (1.20. ApWC/100 + sp) 3*7 _ *l1 +0.0032 (40-WC il I MAX FLOW Ap op 117.0 -0.e32 1.s09

)

112.0 -0.s02 1.747 <

- 1.s -

107.0 -0.sse 1.as7 1 102.s - 0.s71 1.ess j

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1.5 -

MAXIMUM FLOW RATE = 117.0% I 112.0 % 1 107.0% l 102.s%

1.4 -

1.3 -

, 1.2 -

l 3,3 I I I l I I I I I 20 30 40 50 80 70 80 50 100 110 120 CORE FLOW (% totedl

'Ihis figure is referred to by Technical Specification 3.2.2.1 1

K:CONTRouDOCUMBmB2Cl2VXX RODLRB212.WPD e

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l CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF 2495.0083 l B2C12 Core Operating Limits Report Page 17, Revision 0 l

Figure 12 Power - Dependert MCPR Limit, MCPR (P) i k I; RATED MCPR iniULTIPLIER IKpl = j Z l vi 2.3 -

an

"  ! > EO% CORE FLOW OPERAM LitalT BACPR (P) = K,

  • OPERATING LaitT MCPR (100) 2.2 -

l g l FOR P < 25W NO THERMAL LIMITS MONfTORING REQUIRED g_ _ g NO LIMITS SPECIFIED l l FOR 25% 5 P s P  :(P m = 30%)

, 2.0 - l K, = MAXIMUM OF 1.481 OR Ku

! s 50% CORE FLOW Ku = [K, + 0.02 (30% - P)] / OLMCPR(100) p I8 ~

l l K, = 1.9 FOR s 50% CORE FLOW 2.2 FOR > 50% CORE FLOW

  1. 1.8 -

FOR 30% 5 P < 45%:

A K, = 1.28 + 0.0134 (45% P) 1.5 -

be- FOR 45% $ P < 60%:

'g _

K, = 1.15 + 0.00867 (60% P)

FOR 60% s P:

l g 1.3 -

l K, = 1.0 + 0.00375 (100% P) l 1.2 -

l l e , , i W i.1 -

l l 1 S I l l I I I I I I I l1.020 25 30 40 50 60 70 80 90 100

% SS POWER (% rated)

This figure is referred to by

- Technical Specification 3.2.2.1 K:CONIROL\DOCUMDmB2Cl2CX.R\COLRB212.%TD

CP&L Nuclear Fuels Mgmt & Safety Analysis File: NF-2495.0083 B2C12 Core Operating Limits Report Page 18, Revision 0 ,

Table 2 RBM System SetpointS Sggggt Trin Retnnint Allowahle Value Lower Power Setpoint (LPSP') 27.0 s 29.0 ,.

Intermediate Power Setpoint (IPSP') 62.0 s 64.0 High Power Setpoint (HPSP') 82.0 s 84.0 i

Low Trip Setpoint(LTSP) s 115.1 s 115.5 l

Intermediate Trip Setpoint(ITSP) s 1093 s 109.7 I i High Trip Setpoint (HTSP) s 105.5 s 105.9 to s 2.0 seconds s 2.0 seconds Setpoints in percent of Rated 'Ibermal Power.

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

1

'Ihis table is referred to by Technical Specification 33.4 (Tabic 33.4-2)

K: CON 11tOL\DOCUMDmB2C12COLRKXX.JtB212.WPD

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l l ENCLOSURE 2 l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD i LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT J

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i SUPPLEMENTAL RELOAD LICENSING REPORT I

FOR

! BRUNSWICK STEAM ELECTRIC PLANT UNIT 2

RELOAD 11, CYCLE 12 24A5195, REVISION 0 t ,

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