ML20247N750

From kanterella
Jump to navigation Jump to search
Rev 0 to BSEP Unit 1,Cycle 12 Colr
ML20247N750
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 04/30/1998
From: Money M, Siphers J
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20013J582 List:
References
1B21-0537, 1B21-0537-R00, 1B21-537, 1B21-537-R, NUDOCS 9805270218
Download: ML20247N750 (19)
v • d • e


Text

_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ ._ . _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _ _ _ . _ _ _ _ _

ENCLOSUREI BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325 LICENSE NO. DPR-71 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT I

i

! BRUNSWICK UNIT 1, CYCLE 12 CORE OPERATING LIMITS REPORT APRIL 1998 i

e . m a_

w__=__-_________:_ _ . _ - - _

I f

l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1821-0537 B1C12 Core Operating Limits Report Page 1. Revision 0 l BRUNSWICK UNIT 1, CYCLE 12 CORE OPERATING LIMITS REPORT April 1998 I

l

)

Prepared By: aAAA b, (MM Date: Af71f96 (dary V. Money C Approved . Date: 78 98

' I John T. SI%ers Superintendent BWR Fuel Engineering  ;

1

\WT000104'NUCLEARFUELS\ CONTROL \DOCUMENTiB1 C12COLRE1 C12.,COLR. DOC l

I i

L

- CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.18210537 B1012 Core Operating Limits Report Page 2, Revision 0 LIST OF EFFECTIVE PAGES

~ Page(s) Revision 1-18 0

)

W0001NLECONTROLMOCUMEf@B1C12COLRWIC12_COLR. DOC rh

l

. CP&L Nuclear Fuels Mgmt. & Safety Analysis . Design Calc. No. 1821-0537 B1C12 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 1, Cycle 12 as required by Technical Specification 6.9.3.1. The values of the Average Planar Linear Heat Generation Rate (APLHOR) 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 am provided as required by Technical Specification 6.9.3.1.d.

L . .

l- 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 l analysis are met.

i Preparation of this report was performed in accordance with Quality Assurance requirements as 4 specified in Reference 1. )

I~

APLHOR LIMITS r

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 1 through 8. These values were determined with the SAFER /GESTR LOCA methodology described in GESTAR-II

- (Reference 2). Figures 1 through 8 are to be used when hand calculations are required as specified in Technical Specification 3.2.1. ,

I 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 minimum of MAPLHGR(F) determined from Figure 9 and MAPLHGR(P) determined from Figure 10 is used to determine the goveming limit.~

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 methodology and GEXL-PLUS critical power conelation described in GESTAR-II (Reference 2)' i

-and are - consistent g with the Safety. Limit MCPR of 1.09 specified- by Technical

- Specification 2.1.2.

The core flow and core power adjustment factors for use in Technical Specification 3.2.2.1 are

wn000104WUCLEARFUELS\CONTROLVX)CUMEfmB1C12COLR$1C12_COLR. DOC

=- -

l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1B21-0537 B1C12 Core Operating Limits Report Page 4 Revision 0

)

presented in Figures 11 and 12. For any given flow / power state, the maximum of MCPR(F) determined from Figure 11 and MCPR(P) determined from Figure 12 is used to determine the governing limit.

ROD HLOCK INSTRUMENTATION SETPOINTS i 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 correlation described in GESTAR-II (Reference 2).

REFERENCES l 1) BNP Design Calculation IB21-0537," Preparation of the BICl2 Core Operating l Limits Report," Revision 0. April 1998.

2) NEDE-24011-P-A; " General Electric Standard Application for Reactor Fuel;"

(latest approved version).

i i

\\NT000104\NUCLEARFUELS\\ CONTROL \DOCUMENTiB1C12COLR\B1C12.COLR DOC

l .

4 j

l f .

l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0537 B1C12 Core Operating Limits Report Page 5, Revision 0 i

Figure 1 Fuel Type GE10-P8HXB322-11 GZ-70M-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 1

j- This Figure is Referred To By 13.0 Technical Specification 3.2.1 12.0 N

11.0

/ N o

^

Exposure Umit I h

x (GWd/MT) 0.00 (kW/ft) 10.84 88

{ Permissible Reg, ion of b 2.20 11.08

'O ec 9.0 3.31 4.41 11.21 11.35 Operation

\

3 A-5.51 11.50 6.61 11.67 4 7.72 11.92 8.82 12.26 8.0 9.92 12.61 11.02 12.95 13.78 13.12 16.53 12.89 7.0 22.05 12.29 27.56 11.67 33.07 10.96 38.58 10.26 9 44.09 9.52 6.0 49.60 8.78 55.12 6.29

. 5.0 1 0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)

CP&L Nuclear Fuets Mgmt. & Safety Analysis Design Calc. No. 1821-0537 B1C12 Core Operating Limits Report Page 6, Revision 0 Figure 2 Fuel Type GE10-P8HXB320-11GZ-100M-150-T (GE8x8NB-3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 This Figure is Referred To By 13.0 Technical Specification 3.2.1 12.0 J '

11.0 -

N \

\

E Exposure Limit 5 (GWd/MT) (kWMt) 6 0.0 1 0.00 10.81 I: 0.22 10.87 1.10 10.97 l 2.20 11.10

$ 9.0 3.31 11.24 \

Permissible 5 11.

Reg, ion of

< 6.61 11.68 7.72 11.84 Operation 8.0 8.82 12.00 9.92 12.16 11.02 12.33 13.78 12.52 16.53 12.40 7'0 22.05 11.93 27.56 11.44 33.07 10.85 38.58 10.26

  • 6.0 44.09 9.47 49.60 8.68 55.12 6.15 I I

'5.0  !

O 5 10 15 20 25 30 35 40 45 50 55 60 i AVERAGE PLANAR EXPOSURE (GWdMT) 1

l ,

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.18214537 B1C10 Core Operating Limits Report Page 7. Revision 0

, Figure 3 Fuel Type GE10-P8HXB346-12GZ-100M-150-T (GE8x8NB-3) l Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 This Figure is Referred To By 13.0 Technical Specification 3.2.1 12.0 g s

11.0 -

- Exposure Umit f

.g w 10.0 (GWd/MT) (kWMt) 0.00 0.22 10.92 10.95 . w E 1.10 11.04 Perm.issible Region of

$ 2.20 3.31 11.21 11.41 Operation g.

C 9.0 4.41 11.65 5

n.

4 5 51 6.61 11 80 12.08 h 7.72 12.26 k 8.82 12.47 \

8.0 9.92 12.71 11.02 12.94 13.78 12.86 16.53 12.73 7.0 22.05 12.05 _

27.56 11.33 \

33.07 10.69 )

38.58 10.06

  • 44.09 9.41 6.0 49.60 8.76 55.12 6.46 5.0 0 5 10 15 20 25 30 35 40 45 50 55 60 AVERAGE PLANAR EXPOSURE (GWd/MT)  ;

i CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1821-0537 B1C12 Core Operating Limits Report - Page 8, Revision 0 Figure 4 Fuel Type GFliO-P8HXB346-12GZ-100T-150-T (GE8x8NB-3) l Average P!anar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure l

l 14.0 l l This Figure is Referred To By 13.0 Technical Specification 3.2.1 12.0 M, 11.0

^

g a

[ Exposure (GWdMT) ' (kWMt)

Umit \

N g 0.00 10.54  % .

0.22 10.57 T 6 10.0 1.10 10.66 b Permissible h

$ 2;2 1 j2 Region of oc 4.41 11.25 Operation 0 9.0 5.51 11.49 3 6.61 11.66 l Q- 7.72 11.84

  1. 8.19 11.90 8.82 11.94 8.0 9.92 12.03 11.02 12.12 13.78 12.10 16.53 11.75 7.0 21.64 11.17

(

22.05 11.12 27.56 10.75 38.58 10.28 48.26 10.21 6.0 49.60 9.88 53.55 8.57 56.41 6.33 5.0  !

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

1 i

l

i CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1B21-0537 j B1C12 Core Operating Limits Report Page 9, Revision 0 Figure 5 l 1 Fuel Type GE13-P9DTB380-11G5.0-100T-146-T (GE13) j

)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 j This Figure is Referred To By 13.0 Technical Specification 3.2.1 M

12.0 g

/ \,

11.0 1 -

Exposure 1.imit E

(GWd/MT) (kW/ft) 0.00 10.94

\

3: 0.22 10.99 6 10.0 1.10 11.11 t:- 2.20 11.29 i E 3.31 11.49 8

4.41 11.70 EI' 0 9.0 5.51 6.61 11.90 12.07

\

b 7.72 12.24 k- 8.82 12.38 Permissible 9.92 12.50 Region of 1 8.0 11.02 12.61 s j 13.78 12.66 Operation 16.53 12.39 l 19.29 12.03 22.05 11.66 7.0 27.56 10.93 3 33.07 10.21 38.58 . 9.51 44.09 8.82 6.0 49.60 8.15 55.12 7.48 60.63 6.80 63.68 6.41 5.0  !  !  !

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

I l

l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1B21-0537 l B1C12 Core Operating Limits Report Page 10, Revision 0 Figure 6 l

1 l

Fuel Type GE13-P9DTB380-10G5.0-100T-146-T (GE13) l Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 This Figure is Referred To By i 13.0 Technical Specification 3.2.1 D

12.0 11.0 5

Exposure Umit \

(GWd/MT) - (kW/ft) 0.00 11.17 0.22 11.20 3: 1.10 11.32

- 10.0 2.20 11.49 6 3.31 11.68 3 4.41 11.88 3 5.51 12.03 E

9.0 6.61 12.14 k 7.72 8.82 12.25 12.36 g

g

< 9.92 12.47 11.02 12.59 Permissible 13.78 12.65 '

8.0 Region of 22.05 11.67 27.56 10.94 7.0 33.07 10.22 3 38.58 9.52 -

44.09 8.83 49.60 8.15 6.0 55.12 7.48 60.63 6.80 63.56 6.43 5.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWd/MT) l

I f

i l.

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0537 G1C12 Core Operating Limits Report Page 11, Revision 0

j. Figure 7 Fuel Type GE13-P9DTB403-5G6.0/7G5.0-100T-146-T (GE13)

- Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 l

13.0 This Figure is Referred To By i Technical Specification 3.2.1

^ ^

12.0 ,--

11.0 -- ~ Egosure Umit

_ a (GWdMT) (kW/ft) 0.00 10.65 0.22 10.72 1.10 10.85 V

- 10.0 b: 2.20 11.00 2 3.31 11.12 3 4.41 11.25 E 5.51 11.38 Permissible 9.0 6.61 11.52 Region of 3 g 7.72 11.66 Operation

< 8.82 11.81 9.92 11.95 8.0 11.02 12.05 \

13.78 12.04 16.53 11.97 19.29 11.79 22.05 11.54 -

7.0 27.56 11.02 33.07 10.44 38.58 9.69 44.09 8.98 6.0 49.60 8.30 55.12 7.64 60.63 7.00 64.48 6.54 5.0  !  !  !  !

O 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWd/MT) 4 A-& _____J_________ _

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1821-0537 B1C12 Core Operating Limits Report Page 12. Revision 0 Figure 8 Fuel Type GE13-P90TB403-7G6.0/7G5.0-100T-146-T (GE13)

Average Pianar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure l 14.0 13.0 This Figure is Referred To By Technical Specification 3.2.1 12.0 , , ,

r - 'n 11.0 Exposure Umit x

3 (GWd/MT) (kW/ft) a 0.00 10.44 0.22 10.51 10.0 1.10 10.61 \

b 3

2.20 3.31 10.74 10.88 K ]

3 4.41 11.02 tt 5.51 11.17 0 9.0 6.61 11.32 5 7.72 11.48 Permissible

$ 8.82 11.62 Region of 9.92 11.02 11.73 11.85 Operation \N 8.0 --

13.78 16.53 11.86 11.86 h 3 j

19.29 11.76 , l 22.05 11.54

  • 7.0 27.56 11.02 33.07 38.58 10.49 9.85

\

  • 44.09 0.13 49.60 8.43 6.0 55.12 7.73 60.63 7.03 64.29 6.56 5.0  !  !  !

O 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWdMT)

~

I L

l l CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0537 I- B1C12 Core Operating Limits Rep Page 13, Revision 0 l

Figure 9 l

Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10 l

1.00 Max Flow = 102,5% /

/ /

0.90 1' 7%

This Figure is Referred To By I Technical Specification 3.2.1 g 0.80 , ,

N iE R

0.70 -

< MAPLHGR(F) = MAPFACr

  • MAPLHGRsm 2 MAPLHGRsm = Standard MAPLHGR Limits MAPFACr(F) = Minimum (1.0, ArWc/100+Br) 0.60 f w e= % Rated Core Flow Ar And Br Are Fuel Type Dependent Constants Given Below:

Max Core Flow

(% Rated) Ar Br 0.50 102.5 0.6784 0.4861 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.40 -

30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

I I

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc No.1B21-05?7

BIC12 Core Operating Limits Report Page 14, Revision 0 Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.00

/

This Figure is Referred To By

/

l Technical Specification 3.2.1 ,

l 0.90 ,

/

/

a 1 /

/r

o. 0.80 g E

8 /

1 7 8

5 0.70 /

/

a. /

i - f Core Flows 50%

0.60 ' MAPLHGR(P) = MAPFACr

MAPLHGRsm = Standard MAPLHGR Limits i [Il ,

For P < 25% : _

l No Thermal Limits Monitoring Required i For 25% s P < 30% :

i For Core Flow s 50%,

0.M ~

MAPFACr = 0.585 + 0.005224 (P-30%)

For Core Flow > 50%.

Core Flow > 50%

MAPFACr = 0.433 + 0.005224 (P-30%) ~

)g l For P;t 30%:

MAPFAC, = 1.0 + 0.005224 (P-100%)

I I 0.40  !  !  !  !  !  !

20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 1M Power (% Rated)

l l

\

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No.1B21-0537 B1C12 Core Operating Limits Report Page 15 Revision 0 Table 1 MCPR Limits Non-pressurization Transient MCPR Limits l

l Exposure Range Fuel Type BOC-EOC GE8x8NB-3 1.26 GE13 1.26 Pressurization Transient MCPR Limits Exposure Range MCPR Option Fuel Type BOC to EOFPC-2205 EOFPC-2205 mwd /MT mwd /MT to EOC A GE8x8NB-3 1.40 1.46 GE13 1.40 1.45 B GE8x8NB-3 1.35 1.38 GE13 1.35 1.38 This table is referred to by Technical Specifications 3.2.2.1 and 3.2.2.2.

i

\WT000104NNUCLEARFUELS\ CONTROL \DOCUMEtmB1C12COLRB1C12_COLR. DOC 1

- _ - - _ - - _ _ _ - _ i

i L

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0537 B1C12 Core Operating Limits Report Page 16, Revision 0 Flow-Dependent MCPR Limit, MCPR(F) i 1.80 l l l l l l j For Wc (% Rated Core Flow) < 40%, j MCPR(F) = (ArWc/100+ Br)*[1 +0.0032 (40-Wc)]

1.70 For We (% Rated Core Flow) 240%,

MCPR(F) = Max (1.20, A,Wc/100+Br)

Max Core Flow 1,60 .\ (% Rated) Ar Br 102.5 - 0.571 1.655 107.0 - 0.586 1.697 112.0 - 0.602 1.747 117.0 - 0.632 1.809 1.50 ,

s --- N E

o 1 40 s

3 This Figure is Referred To By Technical Specification 3.2.2.1 Max Flov' = 117%

1.30 '

107 % T 102.5 %

1.20 1.10 20 30 40 50 60 70 80 00 100 110 120 Core Flow (% Rated) l l

_ _ _ _ 1

l

! CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0537 B1C12 Core Operating Limits Report Page 17, Revision 0 l

l Figure 12 i

Power - Dependent MCPR Limit, MCPR (P) 2.50 , ,

OLMCPR 2.40  : :  : Rated MCPR Multiplier (Kp)  ;

2.30 f __ Core Flow > 50%

n g 2.20 Operating Limit MCPR(P) = Kp* Operating Limit MCPR(100) -

vi 1 For N 25% .

2.10 No Thermal Limits Monitoring Required o

g No Limits Specified For 25% s P s Payriss : Where Peyriss = 30%

c 2.00 _

Core Flow s 50% Kp = Maximum of 1.481 or Krue

[ . g Ket,, = [Kay, + 0.02 (30% - P)] / OLMCPR(l00) 90 O KBYr = 1.90 For Core Flow s50%,

  • 2.20 For Core Flow > 50%

x 1.80 For 30% s P < 45% :

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

For 45% s P < 60% :

[l { K, = 1.15 + 0.00867 (60% - P)

~

For P 260% :

y 1.60 Kp = 1.00 + 0.00375 (100% - P) -

n Al 1.50 ,,,

i

!!!. 1.40

\ '

hc.

E (

ll 1.30 This Figure is Referred To By Technical Specification 3.2.2.1 3 \

1a 1*10 N ' '

s ,

N N

1.00 N A 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 PsVPASS Power (% Rated)

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1821-0537 B1C12 Core Operating Limits Report Page 18, Revision 0 Table 2 RBM System Setpoints Setpoint Tr!p Setpoint Allowable Value Lower Power Setpoint (LPSP*) 27.0 s 29.0 l Intermediate Power Setpoint (IPSP*) 62.0 5 64.0 High Power Setpoint (HPSP') 82.0 s 84.0 D

Low Trip Setpoint (LTSP ) 5 115.1 5 115.5 D

Intermediate Trip Setpoint (ITSP ) s 109.3 5 109.7 b

High Trip Setpoint (HTSP ) $ 105.5 s 105.9 td2 5 2.0 seconds s 2.0 seconds Setpoints in percent of Rated Hermal Power.

Setpoints relative to a full scale reading of 125. For example, s 115.1 means 5115.1/125.0 of full scale.

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

YNT000104WUCLEARFUELS\\ CONTROL \ DOCUMENT \B 1 C12COLR'81 C12_COLR. DOC

._ _ _ . _ - - - _ _ - - - - _ _ . - _ _ - _ _ _ _ _ - _ _ _ _ -

Retrieved from "https://kanterella.com/w/index.php?title=ML20247N750&oldid=3154630"