ML20211N417

Rev 0 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr

ML20211N417
Person / Time
Site:	Brunswick
Issue date:	09/30/1997
From:	Money M, Siphers J CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20046D886	List: BSEP-97-0442, Forwards Rev 0 to Brunswick Unit 2,Cycle 13 COLR, Rev 1 to 24A5412, Suppl Reload Licensing Rept for BSEP Unit 2 Reload 12 Cycle 13, & Proprietary NEDC-31624P,rev 4, LOCA Analysis Rept for BSEP Unit 2.... NEDC-31624P Withheld ML20211N417 ML20211N424
References
2B21-0088, 2B21-0088-R00, 2B21-88, 2B21-88-R, NUDOCS 9710160128
Download: ML20211N417 (19)

Text

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CP&L Nuclear Fuels Mgmt & Safety Analysis DC #; 2B2l4)88 D2Cl3 Core Operating Limits Report Page I, Revision 0 BRUNSWICK UNIT 2, CYCLE 13 l CORE OPERATING LIMITS REPORT Septemher 1997 i

Prepared By: GM k .JU Alft9 Date: I/20/@

MSry V. Money (

Approved B v du h Date:

Joh'iiT. Siphe.s /'

Superintendent BWR Fuel Engineering K:\ CONTROL \ DOCUMENT \B 2C l 3\COLR\COLR. DOC hDR 0 050bO324 p PDR t 7

CP&L Nuclear Fuels Mgmt & Safety Analpis DC #: 20214X)88 B Cl3 Core Operating Limits Report Page 2, Reusion 0 LIST OF EFFECTIVE PAGES P.algtW Revision 1 18 0 K ACONTROL\DOCUM ENnB 2Cl 3\COLR\COLR. DOC

CP&L Nuclear Fuels Mgmt & Safety Analysis DC #: 2B21&M8 B2Cl3 Core Operating Limits Report Page 3. Revision 0 INTRODUCTION AND SUMNIARY This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 13 as required by Technical Specification 6.9.3.1. The 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 6.9.3.1.a. The values of the Minimum Critical Power Ratio (MCPR) limits, along with associated core flow and core power adjustment factors are provided as required by Technical Specifications 6.9.3.1.b and 6.9.3.1.c. The control rod block upscale trip setpoints and allowable values are provided as required by Technical Specifiestion 6.9.3.1.d.

Per Technical Specifications 6.9.3.2 and 6.9.3.3, these values have been determined using NRC-approved methodologies and are established such that all applicable limits of the plant safety analysis are met.

Preparation of this report was performed in accordance with Quality Assurance requirements as specified in Reference 1.

APLHOR LIMITS The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average exposure is given in Figures I through 8. These values were determined with the SAFER /GESTR LOCA methodology described in GESTAR-II (Reference 2). Figures I through 8 are to be used when hand calculations are required as specified in Technical Specification 3.2.1. Also, the lattice dependent APLHGR limits loaded in the process computer databank should be obtained from the design calculation documenting the generation of that dctabank.

The core flow and core power adjustment factors 'or use in Technical Specification 3.2.1 are presented in Figures 9 and 10. For any given flow / power state, the minimum of MAPLHGR(F) determined from Figure 9 and MAPLHGF.(P) dr.termined from Figure 10 are used to determine the governing limit.

MCPR LIMITS Tla ;YN OPTION A, ODYN OIrTION B, and non-pressurization transient MCPR limits for use in iecuaical 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 itermined with the GEMINI method-ology and GEXL-PLUS critical power correlation descid in GESTAR-II(Reference 2) and are K;\ CONTROL \DOCUMENITB 2C l 3\COLR\COLR. DOC

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

L 4

CP&L Nuclear Fuels Mgmt & Safety Analysis DC *: 2B210088 B2Cl3 Core Operating Limits Report Page 4. Revision 0 consistent with the Safety Limit MCPR of 1.09 specified by Technical Specification 2.1.2, The analyses were performed witho n End of Cycle Recirculation Pump Trip (EOC RPT) operable, i

The 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),

I determined from Figure 11, and MCPR(P), determined from Figure 12, are used to determine the governing limit, 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.

r 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 correlation described in GESTAR il(Reference 2).

4 REFERENCE (s) 1-3 1) Design Calculation 2B21-0088, " Preparation of the B2Cl3 Core Operating Limits

. Report," Revision 0, September 1997.

! 2) . NEDE 240ll P-A; " General Electric Standard Application for Reactor Fuel:" (latest

approved version),

4 i.

1_

l l

1_

i l- KACONTROL\DOCUMENnB 2C l 3\COLR\COLR. DOC t

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CP&L Nuclear Fuels Mgmt & Sofety Anolysis D.C.f 2B21-0088 B2C13 Core Operating Limits Report Page 5 Revision 0

('

Figure 1 FUEL TYPE GE10-P8HXB329-12GZ1-100M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 TH!S FIG JRE IS Rt. t.nEC TC BY Tl:CH %LSPECIFHXTON 3.2,1 l 13

( N

/ N 12 r y

/ N 11

/ PEFMISSIB.E REC l_ON _Off \s vr.- ,vn -

R '

N

• 3, ~.=> - ..m N

[GWd/h4 (kW/ft) \

o 0.00 u

10 52 e

\

'_ 9 19 x

$ f.i5 i5 63 N1 z J.31 11 17

-J 4.41 11 35

(

k 5.51 11 53

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Mi 8.82 Ii M \

12 12 9.92 12 37 3 7

11 .02 13,75 12 63 12 52

\

l 16,53 12 65 l 22.05 12 13 6

49,60 8 63 6 55,67 5 90 5 ,

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

CP&L Nuclear Fuels Mgmt & Sofety Analysis 0.C.f 2821-0088 B2C13 Core Operating Umits Report Page 6. Revision 0 Figure 2 FUEL TYPE GE10-P8HXB324-12GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THIS FIG JRE IS RETRRED TC BY Tl:CHilChLSPECIFICATDN 3.2,1 13-A l [ N 2

/ PEF'Wi!SIBI N\

12 '

REC IOh Ol'

[ OPl:RN10h

/ \

2 11 - N

% / N

$ gPDSL RE UI \

,Gws/hT) (ku/ft)

{' \

E til a fi \

1.10 2.20 10 87 11 07 k 5 9 i'fi ii i$ -

$ 5 ..51 11 83 6.61 12 02 7,72 12 22 8 '

11 .02 12 96 13,78 13 17 18,53 12.93 22.05 12 27 (

27,56 11 62 7 aa.u i i v.v,

\

38,58 10 27 44,09 9 52 49,60 8 78 "

55.12 6 27 6

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

CP&L Nuclear Fuels Wgmt & Safety Analysis D.C,f 2B21-0088 B2C13 Core Operating umits Report Page 7 Revision 0 Figure 3 FUEL TYPE GE10-P8HXB320-11GZ-100M-150-T (GE8X8NB-3)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE P(APLHGR) LIMIT LANAR EXPOSURE 14 TlilS FIG JRE IS RETRREC TC BY Tl:CH ilCALtiPECIFICAT1')N 3.2 1 13 J \

l'ERMISlilCLE ItEGION OF

, OPEItAT10N f \

x ~XPOSURE UldIT \

{ IGwd/hT) (w/ft) g 3 c:E 1 .10 10 E 10 97 N

$ 2.20 11 10 5 9 i:ll ii $-! \

$ 5.51 6.61 11 53 11 68 7.72 11 84 8

i 11 ,02 12 33 13.78 12 52 18.53 12 40 22.05 11 93 L 7

27.56 11 44 \

ga,v f iv og 38.58 10 26 44,09 9 47 49.60 8 68 55.12 6 15 a 6

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

i CP&L Nuclear Fuels Mgmt & Sciety Analysis 0.C. 2B21-0088 B2C13 Core Operating umits Report Pagel8, Revision 0 Figure 4 FUEL TYPE GE10-P8HXB322-11GZ-70M-150-T (GE8X8NB-3)

AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 TlilS FIGlJRE IS RETRREO TC B1 Tl:CH ilCALSPECIFICAT!ON 3.2,1 13 A

T I N N

12- --

I k!GWY '%

/ o>EMTION-

\

11

/ N

1. N

($ OSI.lRE UldlT \

M*P

,G d/hT) (w/ft) K

{' g li \

a 8:si 1 .10 2.20 10 95 11 08 k 9

5.51 d.61 7.72 11 11 11 50 67 92

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11 .02 12 95 13.78 13 12

. 16.53 12 89 22.05 12 29 (

7 27.56 11 67 \

aa.u t iv vo 38.58 10 26 44.09 9 52 49.60 8 78 9' 55.12 6 29 6

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

CP&L Nuclear Fuels Mgmt & Safety Anolysts 0.C.f 2821-0088 82C13 Core Operating umits Report Page 9. Revision 0 Figure 5 FUEL TYPE GE13-P9DTB363-11GZ1-100T-146-T (GE13)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THIS RGURE' IL REFE RRED TO ErF TECHMCJLliPE CIFICATlON<5.2 1 13 M

3 l \

[ PEltMISSI BLE REGIONOF N

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l 9 gg D POSultE .LIMr

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8 bbli5 17.b6 1 I3 i b 33.07 1 1.1 6 10.4,5 \

7 iH2 H! \.

<9.ie si x 55.< 2 7.75 10.03 tC9 7.04 \ >

5.44 6 ,

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

CP&L Nuclear Fuels Mgmt & Sofety Anolysis D.C. 2821-0088 B2013 Core Operating umits Report Pagel10, Revision 0 Figure 6 FUEL TYPE GE13-P9DTB363-11GZ-100T-146-T (GE13)

AVERAGE Pl.ANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THIS RGI)RE' It REFI RRED TO BY TECHMCAL 3PE CIFICATION,5.2 1 13-D  %

,2 >l N

[ PEItMISSI M.E h

/ REGIO 4 OF OP ERATlON \

, r c gg D POSUltE I.lur' .

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t= ER 1

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!' ini i i;65 4.61 1 1.3) k at:

0 5.fil 6.01 1 1.9i 1:2.11) y 5 , 7.v2 -

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< 9.112 1:.2.45 1 1.02 1:t.$I \

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<s.oo si s

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05.26 5.46 6

0 5 10 15 20 25 30 35 40 45 50 55 60 6S' 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

CP&L Nuclear Fuels Mgmt & Sofety Analysis D.C.f 2B21-0088 82C13 Core Operating Umits Report Page 11 Revision 0 Figure 7 FUEL TYPE GE13-P9DTB395-12G5.0-100T-146-T (GE13)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) UMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THISl~lGURE: I! REFE RRED TO Err TECHellCA! 3PE:CIFICAT104<5.2 1 13 12

/ PEltMISSI BLE

/ REGIO 4(F f OPERATICN \

2 11 ^^

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. . \

N (O GWd/M") (LW/ft) \

5 \s 6 0.(C 1 1.1 5 0.:t2 1 1.2 4  %

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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 Mgmt & Safety Analysis 0.C.f 2821-0088 82C13 Core Operating umits Report Page 12 Revision 0 Figure 8 FUEL TYPE GE13-P9DTG393-4G6.0/9G5.0-100T-146-T (GE13)

AVERAGE Pl.ANAR LINEAR HEAT GENERATION RATE (APLHGR) LIMIT VERSUS AVERAGE PLANAR EXPOSURE 14 THISl%URE: 11 REFI RRED TO Err TECHMCJL 3PE CIFICATION .5.2 I 13 l,

,2 - .;

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04.1 4 1 5.45 6

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

CP&L Nuclear Fuels Mgmt & Safety Analysis DC w. 2B2100x8 B2Cl3 Core Operating Limits Report Page 13. Reusmn 0 Figure 9 Flow - Dependent MAPLHGR Limit, MAPLHGR (F) 1.0 -

04

/f,.

0.e - +# *~, $*

o.s -

S MAPLHGatPl=MAPPACp a MAPLMGas TO MAPu<insTo-sTANoAno uAPLHon uuiTs MAPPAc,tP)-unuuu it.0, A,w s100e + api

!o,7 we* nATso cons Ptow ANo A ,PSp AnE PUEL TYPE DEPENOGNT CONSTANTS GIVEN BELow:

0e MAXIMUM CONE PLOW i% retoe Ap Sp 0' ~ 102.s 0.4764 0.4481 107.o 0.e76a 0.4s74 112.0 0.6407 0.4214 117.0 0.8886 0.3428 0.4 I I I I I I I 30 40 50 60 70 80 90 100 110 cons Ptow tu rose This figure is referred to by Technical Specification 3.2.1 K:\ CONTROL \ DOCUMENT \B2C l 3\COLR\COLR. DOC

CP&L Nuclear Fuels Mgmt & Safety Analysis DCw: 2021 WS8 B2Cl3 Core Operating Limits Report Page 14. Reusion 0 1

Figure 10 Power - Dependent MAPLHOR Limit, MAPLHGR (P) 1.0 O.s -

I

!. 5 0.s

uan.eAm.MamC, uAPuen,To 0.7 ~ s50% COME PLOW MAPLHOAST0 = 3TANDAA0 MAPLHOR UMITS i POR 25% >P

NO THEAMAL UMITS MONITORING E REQUIAGO -

I 0.6 - c M 28% sPG%:

i MAP 8ACp = 0.588 + 0.008224 (P- 30%)

, FOR s 50% CORE PLOW MAPPACp = 0.433 + 0.004224 (P- 30%)

J l > S0% COME PLOW POR > SO% CORE PLOW 0.5 - g e

, g e POA 30% s P.

I MAPPACp = 1.0 + 0.006224 (P- 100%)

I o,4 I I I I i l l 20 25 30 40 50 60 70 80 so 100 POWEA (% rated i

This figure is referred to by Technical Specification 3.2.1 4

K:\ CONTROL \DOCUMENI\B 2Cl 3\COLR\COLR. DOC i

i

i I

CP&L Nuclear Fuels Mgmt & Safety Analysis DC#: 2B210088 B2Cl3 Core Operating Limits Repon Page 15, Revision 0 Table 1 MCPR Limits (EOC.RPT Not Required)

Non-pressurization Transleiit MCPR Limits Fuel Type MCPR Limit Exposure Range GE8x8NB 3 1.29 BOCl3 EOCl3 gel 3 1,29 BOCl3 EOCl3 Pressurization Transient MCPR Limits MCPR Option A Fuel Type MCPR Limit Exposure Range GE8x8NB-3 1.35 BOCl3 to EOCl3 2205 mwd'MT GE13 1.35 BOCl3 to EOCl3 2205 mwd'MT GE8x8NB-3 1.43 EOC13 2205 mwd %1T to EOC13 gel 3 1.43 EOCl3 2205 mwd'MT to EOCl3 MCPR Option B FuelType MCPR Limit Exposure Range GE8x8NB 3 1.30 BOC13 to EOC13 2205 mwd'MT GE13 1.30 BOCl3 to EOCl3 2205 mwd'MT GE8x8NB 3 1.35 EOCl3 2205 mwd %1T to EOCl3 GE13 1.35 EOCl3 2205 mwd'MT to EOCl3 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2.

K:\ CONTROL \DOCUM ENBB2 C l 3\COLR\COLR. DOC

_ - - .__ - - - . . . . .~. -. .. . - - . . _ . -. -- . . . . , . . . , _ - . -

4 CP&1. Nuclear Fuels Mgmt & Safety Analysis DC#: 2B2100s8 B2Cl3 Core Operating Limits Report Page 16. Resiuen 0 Figure 1I r

Flow - Dependent MCPR Limit, MCPR (F) i 4

4

• FOR Wg (% RATED CORE FLOW) < 40%

MCPRIF) = (ApWC1100 + Sp) POR WC (% RATED CORE FLOW) a 40%

' MCPR(P) = MAX (1,20. ApWC/100 + Spl i,7 _ 'I1 + 0.0032140-WC il 117.0 -0.832 1.809 112.0 - 0.002 1,747 1.3 -

107.0 - 0.586 1.697 102.5 - 0.571 1.055 4

1

• i j,3 -

- MAXIMUM PLOW RATI= 117.0%

112.0 %

107.0 %

102.sm 1,4 =

1.3 =

i 1,2 =

i,, I I I l i I I I I 20 30 40 50 40 70 80 90 100 110 120 coat Plow tu rowe 4

This figure is referred to by Technical Specification 3.2.2.1 i K:\ CONTROL \ DOCUMENT \B2C l 3\COLR\COLR. DOC

CP&L Nuclear Fuels Mgmt & Safety Analysis DC3: 2B210088 B2Cl3 Core Operaung Limits Report Page 17. Regiuon 0 Figure 12 Power - Dependent MCPR Limit, MCPR (P)

{ 2.4 QLucPR RATED MCPR MULflPLifR INpi

, 2.3 =

I I: r e

OPERATING UMIT MCPR(P) = 4

• OPERATING UMIT MCPR(100) 2.2 =

w POR P e 2$%: NO THERMAL UMITS MONITORING REQUIRED g l NO UMITS SPECIFIED 2.1 -

l l POR 25% s P s P ..:(P,,. = 30%)

I I 4 MAXIMUM OF 1.441 OR %

ipI8 '

~

g a 50% CORE FLOW  % =(N.+CM( .

O N R(1 @

" l 4e 19 FOR s 50% CORE Pt.OW q 2.2 POR > $0% CORE PLOW ll

_ l POR 30% s P < 44%:

M p 4 a 126 e 0 0134(44% P)

a. 1,3 -

POR 15% s P < $0%:

! ~

l l 4 = 1.15 + 0.00067(60% . P) fI $ l POR 80% s P:

I i 3,3 _ g ,

4 = 1.0 + 0 00375(100% . P)

.g I . _ .

1.2 =

l l 1.1 =

l l l i

i I l

{1.020 25 30 40 50 i

to 70 I

to 90 100 PBYl%SS POWER 1% reteel This figure is referred to by Technical Specification 3.2.2.1 K:\ CONTROL \DOCUMENI\B 2C l 3\COLR\COLR. DOC

.- .. . - _ . - . .. - - - - --... .. - = .- . _ _ . . -- -

i e

CP&L Nuclear Fuels Mgmt & Safet) Analysis DC#: 2B210088 B2Cl3 Core Operating Limits Report Page 18, Resision 0 Table 2 RBM System Setpoints Setooint Trio Setooint Allowable Value Lower Power Setpoint (LPSP') 27.0 - s 29.0 Intermediate Power Setpoint (IPSP*) 62,0 5640 4 High Power Setpoint '(HPSP') 82.0 s 84.0 t

b

, Low Trip Setpoint (LTSP ) s 115.1 s 115.5 D

iIntermediate Trip Setpoint (ITSP ) s 109.3 s 109,7

'~ D High Trip Setpoint (HTSP ) $ 105.5 5 105.9-ta2 s 2.0 seconds. s 2.0 seconds Setpoints in percent of Rated Thermal Power.

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

4 Y

w 4-3-

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

KACONTROL\DOCUMENnB 2Cl 3\COLR\COLR. DOC 4

+-, -

ENCLOSURE 2 o-

. BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324 LICENSE NO. DPR-62

. TRANSMITTAL OF CORE OPERATING LIMITS REPORT,

< SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT i

e 1

~ 24A5412, REVISION 0 SUPPLEMENTAL RELOAD LICENSING REPORT L FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 2

-RELOAD 12 CYCLE 13

1 i

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e i

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