Text

Rev 0 to Toledo Edison Co Davis-Besse Unit 1 Cycle 10 Colr
	ML20149H140
Person / Time
Site:	Davis Besse
Issue date:	11/11/1994
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20149H138	List: ML20149H135; ML20149H140; ML20149H145;
References
	NUDOCS 9411180067
	Download: ML20149H140 (20)
	v • d • e

._ - - . . -

COLR !

' 'I Page 1 of 20

' ' Revision 0 j 1

l r

TOLEDO EDISON COMPANY i

l DAVIS-BESSE UNIT 1 f CYCLE 10 I i

P CORE OPERATING LIMITS REPORT t

- i i

LIST OF EFFECTIVE PAGES Page C-1 through C-20 Rev. 0 l

9411180067 94j133 DR ADOCK 05000346 C-1 PDR

COLR r : Page 2 of 20 Revision 0 Technical Specification /COLR Cross-Reference Technical Specification COLR Figure / Table 3.1.3.6 Figure la Regulating Group Position and Alarm S2tpoints, O to 25 3.1.3.8 +10/-0 EFPD, Four RC Pumps 3.1.3.6 Figure Ib Regulating Group Position and Alarm Setpoints, 25 +10/-0 3.1.3.8 to 460 10 EFPD, Four RC Pumps 3.1.3.6 Figure Ic Regulating Group Position and Alarm Setpoints, after 460 3.1.3.8 10 EFPD, Four RC Pumps 3.1.3.6 Figure id Regulating Group Position and Alarm Setpoints, O to 25 +10/

3.1.3.8 -0 EFPD, Three RC Pumps 3.1.3.6 Figure le Regulating Group Position and Alarm Setpoints, 25 +10/-0 3.1.3.8 to 460 210 EFPD, Three RC Pumps ,

3.1.3.6 Figure if Regulating Group Position and Alarm Setpoints, after 460 3.1.3.8 10 EFPD, Three RC Pumps 3.1.3.7 Figure 2 Control Aod Co' oocations and Croup Assigny 'ts 3.1.3.9 Figure 3 APSR Position Alarm Setpoints 3.2.1 Figure 4a AXIAL POVER IMBALANCE Alarm Setpoints, O EFPD to E0C, Four RC Pumps 3.2.1 Figure 4b AXIAL POVER IMBALANCE Alarm Setpoints, O EFPD to E0C, Three RC Pumps 2.1.2 Figure 5 AXIAL POVER IMBALANCE Protective Limits 2.2.1 Figure 6 Flux - a Flux /Flov (or Pover/

Imbalance / Flow) Trip Setpoints 3.2.4 Table 1 QUADRANT POVER TILT Limits 3.1.1. 3 c Table 2 Negative Moderator Temperature Coefficient Limit B2.1 Table 3 Power to Melt Limits C-2

Cic.R r : Pags 3 of 20

'

Revision 0 3.2.2 Table 4 Nuclear Heat Flux Hot Channel Factor - F O f 1

3.2.3 Table 5 NuclearEnthalpyRfseHot Channel Factor - F g 3.2.3 Figure 7 Allovable Radial Peak for F" g l

i e

4 o

C-3

COLR

, , Page 4 of 20

,'

Revision O TOLEDO EDIS0N DAVIS-BESSE UNIT 1 l

CYCLE 10 l

CORE OPERATING LIMITS REPORT 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 10 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The core operating limits have been developed using the methodology provided in reference 2.0 (1).

The following cycle-specific core operating limits, Protective Limit and Flux - a Flux / Flow Reactor Protection System Setpoints are included in this report:

1) Regulating Group Position Alarm Setpoints (insertion limits) and Xenon reactivity " power level cutoff"

2) Rod program group positions (Control Rod Core locations and group assignments)

3) Axial Power Shaping Rod Alarm Setpoints (insertion limits)

4) AXIAL POVER IMBALANCE Alarm Setpoints

5) AXIAL POWER IMBALANCE Protective Limits

6) Flux -6 Flux /Flov (or Pover/ Imbalance / Flow) Trip Setpoints

7) QUADRANT POWER TILT limits

8) Negative Moderator Temperature Coefficient limit

9) Nuclear Heat Flux Hot Channel Factor, F9 and

10) Nuclear Enthalpy Rise Hot Channel Factor, F g 2.0 References (1) BAV-10179P-A, Revision 0, " Safety Criteria and Methodology of Acceptable Cycle Reload Analysis."

(2) BAV-2149P-A, Revision 0, " Evaluation of Replacement Rods in BVFC i Fuel Assemblies."

j C4

COLK P2ge 5 of 20 t l Revision 0 Figure la Regulating Group Positlon Alarm 5etpoints O to 25+10/-O EFPD, Four RC Pumps --

Davis-Besse I, Cycle 10 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 IIO >

, q i.

r r POWER LEVEL j! r i00 CUTOFF = I00%

i s i _-Y T l fd ']

s r Wf 90 /

f I

2 O r r a

80 s' !

d UNACCEPTABLE r

/

y OPERATION T 2 'i w 70 / ,

I IOPERATION F / RESTRICTED y

o 60 i gm _,-

p /

H - -

s __,__,_

LLI HARGIN '

/

LIMIT ,

Qg 50 >

e

/

e j ,

, e

+ '

40 l '

s e- /

s f ACCEPTABLE c > < OPERATION -

se o 30 "

OPERATION 4

/

~-PRESTRICTED, ,

+

m 7 Q.

- 20 i iier c \ M' 3 10

\

.o r A/

-e o _____A j' e s v f f f O

?

O 25 50 75 100 125 ISO 175 200 225 250 275 300 Rod Index (% Withdrawn)

O 75 IOO j 1 1 I GROUP 5 0 25 75 i00 I I I l

GROUP 6 0 25 (o0 I I I GROUP 7 Note I- A Rod Group overlap of 2525% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained Note 2: Instrument error is accounted for in these se1 points.

C-5

COLR Page 6 of 20

. Revision 0 FigureIb Position Alarm Setpoints Regulatinq 25+10/-O fo Group 460*lO EFPD, Four RC Pumps Davis-Besse 1 Cycle 10 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 IIO i j

- .m

/ i /'

POWER LEVEL I00 ---- CUTOFF = 100% f n

g i l 1 l

uj 90 / f a i

/ f Q. r 3

80 .---.--.

4 i X i t

ta 70 sa I IOPERATION H _, / RESTRICTED a 60 se - -- --

~~' ~

f '

]b ld MARGIN 3F ~ # s#

F LIMIT \ / m e'

@ 50 \,

j s r e

l s ?

40 \ l , s' UNACCEPTABLE j ,? ACCEPTABLE i

l OPERATION /s/ OPERATION '

o 30 es' u y e s-O. s 20 e 5- e s'

e s y 10 sr o -_-_/_

0. y'r O

O 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index (% Withdrawn)

O 75 100 ,

I I I GROUP 5 0 25 75 100 -

1 I I I GROUP S O 25 IOO I I I GROUP 7 Note l- A Rod Group overlap of 25tS% between sequentlot withdrawn groups 5 1 and 6, and 6 and 7, shott be maintained Note 2: Instrument error is accounted for in these setpoints.

C-6 1 l

i

COLR Page 7 of 20 l

. Revision 0 Figure Ic Requtating Group Position Alarm Setpoints Affer 460ilO EFPD, Four RC Pumps --

Davis-Besse I, Cycle 10 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.l.3.8 l

l10

~-~ POWER LEVEL l00 4_ CUTOFF 100% / [j[

n tr 1

e f.l /

l W 90 ;

i

/ /

J }

o. < .r g 80 /---- f 4

I .--

M i

@ 70 ,

/ /!

I / OPERATION H ' , RESTRICTED f

o 60 SHUT m / / !'

W MARGIN --' ' s' H LIMIT t / '

/ -

'-~~-

@ 50 t 1 /

+ 1 / jf 40 j ;"

._____ UNACCEPTABLE / '

j ACCEPTABLE I

e OPERATION 1 // --

OPERATION u 30 g_f

' ir e s

o. s

- 20 f c

e a r

/

3 10 e o ___g____.

1 737[i

O' O 25 50 75 IOO I25 150 175 200 225 250 275 300 Rod Index (% Withdrawn)

O 75 100 1 I I GROUP 5 0 25 75 100 l l 1 I GROUP 6 0 25 100 l I I GROUP 7 Note I: A Rod Group overtop of 25*5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained Note 2: Instrument error is accounted for in these setpoints.

l C-7

COLR Page 8 of 20 i . Revision 0 Figure ld Regulatinq Group Position Alarm Setpoints O to 25+10/-O EFPD, Three RC Pumps --

Davis-Besse I, Cycle 10 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 ll0 100 n

[

W 90

3c o

Q.

80 ,__ 2 i d

=--POWER LEVEL / f

E :::CUTOFT = 75% g ,e A

T A W 70 1 r

i s r I -

F / [

a 60 r

UNACCEPTAW F l ,

w OPERATION _ e f

F- '

$ 50 j agrion -

/ RESTR,ICTED2 ,

.+- 7 o

49 ,

7 jy r r '

s M

S o 30

-MARGIN LIMIT 2 r f-/ ,

,? "'-d c

o i

i .f j/

f'e ACCEPTABLE OPERATION Q. s -ar

- 20 -

MM --OPERATLON STRIC - M [-

' s I r e i 3 10 N v o __--

o. ___ - ;

2 4 &,- , ,

n O

O 25 50 75 i00 125 I50 175 200 225 250 275 300 Rod Index (% Withdrawn)

O 75 100 I I I GROUP 5 0 25 75 100 -

i 1 1 I

GROUP 6 0 25 100 1 I I GROUP 7 No9e l- A Rod Group overlap of 2525% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained Note 2: Instrument error is accounted for in these setpoints-.

C-8

COLR Page 9 of 20 Revision 0 i .

Figure Ic Regulating Group Position Alarm Setpoints--

25+10/-O to 460*10 EFPD, Three RC Pumps Davis-Besse I, Cycle 10 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.1.3.8 I I10 ,

I i

i i

i 100

[

g 90 O

Q.

80 d $2 POWER LEVEL e

/ rf~------

y, :::: CUTOFF = 75%

T l l w 70 r r

s i

I '

> s l e i g 60 # '

W ----

UNACCEPTAN F f OPERATION r F- , 1 4 50 g / OPERATION-RESTRICTED

, f -

j e

s e

40 r -

SHUTDOWN ___e " se c, MARGIN , '

o 30 LIMIT 1 - - '

c / "

' ACCEPTABLE e t _f,s / OPERATION Q. i _se'

- 20 .e 2 - ,

c ',

e e ,e r 10 "

e

'p?"f

~-

E O

O 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index (% Withdrawn)

O 75 100 I I I GROUP 5 0 25 75 i00 1 I I I GROUP 6 0 25 100 1 1 1 GROUP 7 A Rod Group overtop of 25*5% between sequential withdrawn groups 5 Note I 1

- and 6, and 6 and 7 shall be maintained.

Note 2: Instrument error is accounted for in these setpoints.

C-9

COLR

., ., Page 10 of 20 i

. . Revision 0 Figure if Regulating Group Position Alarm Setpoints After 460*10 EFPO. Three RC Pumps --

Davis-Besse I, Cycle 10 This Figure is referred to by Technical Specifications 3.1.3.6 and 3.I.3.8 I10 ,

100 n

[

g 90 o '

O.

80 d

y is: POWR LEVEL

CUTOFF = 75% f

/1/

i

@ 70 , Ej 1 , r s H '

s /

o 60 UNACCEPTABLE /

f f -

lu F- . OPERATION f -

4 fi g 50 OPERATIM

. RESTRICTED

+- >

J 40 ,

/ s e

~ "'

SHUTDOWN #

5 MARGIN LIMIT

,_ --.__ f ,,e d o 30 i s e-

t. sd ACCEPTABLE Q.

e f 7

// OPERATION

- 20 i s 6,s '~

g e ,/

3 IO s -

O ...__. __ p f" Q. :-;;; /i O

O 25 50 75 100 125 150 175 200 225 250 275 300 -

Rod Index (% Withdrawn)

O 75 i C,0 :

1 I I GROUP 5 O 25 75 i00 -

l 1 I I GROUP 6 0 25 100 l I I GROUP 7 Note I: A Rod Group overlap of 25*5% between sequential withdrawn groups 5 and 6 and 6 and 7, shall be maintained Note 2: Instrument error is accounted for in these setpoints.

C-10

COLR I

Page'11 of 20 Revision 0 Figure 2 Control Rod Core Locations and Group Assignments Davis-Besse I, Cycle 10 This Figure is referred to by Technical Specificotlon 1

3.l.3.7 X

N I

A

~~ ;

B 4 6 4 C 2 5 5 2 D 7 8 7 8 7 E 2 5 5 2 4 8 6 3 6 8 4 F

5 1 1 5 G

6 Y

H- 6 7 3 4 3 7 H

K 5 1 1 5 .

4 8 6 3 6 8 4 L

f1 , 2 5 5 2 ;

7 8 7 8 7 N l 2 5 5 2 0 l l 4 6 4 P l l R l l t i I '

Z 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 ,

X Group Number Group No. of Rods function 1 4 Safety -

2 8 Safety 3 4 Safety ,

4 9 Safety 5 12 Control 6 8 Control 7 8 Control ,

8 _ 8_ APSRs Total 61 1

C-11

COLR Page 12 of 20 Revision 0 Figure 3 APSR Position Alarm Setpoints This Figure is referred to by Technical specification 3 . .i . 3 . 9 Before APSR Pull - 0 EFPD to 460 +/- 10 EFPD,

! Three or Four RC pumps operation

Lower Setpoint: 0%WD _

Upper Setpoint: 100 %WD

! After APSR Pull - 460 +/- 10 EFPD to End-of-Cycle Three or Four RC pumps operation

I Insertion Prohibited per Tech Spec 3.1.3.9 1

~

Power restricted to 77% for 3 pump operation C-12 l I _

COLR Page 13 of 20 }

Revision 0 Figura 4a. AXIAL POWER IMBALANCE Atarm Setpoints ;

O EFPD to EOC. Four'RC Pumps -- 1 l

Davis-Besse 1 Cycle 10 This Figure is referred to by Technical Specification 3.2.I i10 l

1 l l t 00 ', l

'V \'

I 1

2 1

)

/ s 90

/ r 1

/ > n I s e x _.

j

<--80 l 1 5.

k h CTED* '

l 4 I

_ RESTRICTED REGION

. g .

! y I j t. _ .so _.

. o .

I W I F-

! x< -

-50 !

! . ! l L M. _ I 40 i c N

i

[ !._ 30 i

I ' i :

i i ,

__ __ __j 20 j ,

PERMISSIBLE , ,

}' OPERATING i

__j REGION go g i !

I i

-40 -30 -20 -10 O 10 20 30 40 AXIAL POWER IMSALANCE %

LEGEND FULL INCORE

Based on measurement system EXCORE flo t e i Instrument error is accounted for in these setpoints.

C-13

COLR l

Page 14 of 20 Revision 0 Figure 4b AXIAL POWER IMBALANCE Atarm Setpo,nis O EFPO to EOC, Three RC Pumps -- ;

Davis-Besse I, Cycle 10 1

I This Figure is referred f to by Technical Specification 3.2.I ,

i 110 I

lO0 i i

l i

90 80, y ,

n ,

\

j CTED.1

'. h h C E ,

---70 t

g j / / fa g

=

/ / t .; f

(

j---60 m

i I W I

= I '

i i

---50 l8 O

. g -

1 F T i < !

,! m---40 ,! ,

m - in 1 1s o 1 l In la

,' 5---30 i'

! L !! .

i !

i e

.i 3 1 t' o

20 .

$ l

$ f-

!j- PERMISSIBLE- !j l i OPERATING i

.i REGION IO _i r r

's 's i

s t' i 1

-40 -30 -20 -10 O 10 20 30 - 40 !

1 AXIAL POWER IMBALANCE %

LEGEND

Based on measurement system FU_L INCORE EXCORE Note 1. Instrument error is accounted for in these setpoints.

c \h

COLR Page 15 of 20 ,

Revision 0 Figure 5 AXIAL POWER IMBALANCE Protective Limits .

This Figure le referred to by Technical Specification 2.1.2

% RATED THERMAL POWR

--120 (37. 4 ,i12)

(-37.09,i12)

--110

(-51.45,100) __ goo

, (55.21.96.06) 3 PUMP LIMIT 90

(-37.09.89.80) (37.09.89.80)

-- 80

(-51.45,77.00) -

-- 70 _

- - 60

- - 50

-- 40 UNACCEPTABLE UNACCEPTABLE OPERATION i OPERATION

-- 30 l

-- 20 i ACCEPTABLE OPERATION l FOR SPECIFIED RC 1 PUMP COMBINATION -- 1O l

I I I I I I t I f f I

-20 -10 O 10 20 30 40 50 60

-60 -50 -40 -30 ,

I AXI AL POWR IMBALAtCE % .

I Required Measured Reactor Cootant Flow to Ensure )

Pumps Operatin9 Flow. gpm Compliance, gpm l

{

4 380.000 389.500 3 283.860 290.957 C-15

^^ _

COLR q

. , Page 16 of 20 I Revision 0 Figure 6 F L ux-- A Fl u x/F L ow (or Power /Imbatonce/Ftow)

Trip Setpoints ,

t i

This Figure is referred j to by Technical Specification 2.2.I 310 1

' l iiiiirsi illittat N )

/ '

/ 4 PUMP \

\

/ LIMIT gg 3 f \

\

(

90 t x

\

i N 80 & ,

i i 3 ;

j

' T

/ %

N i

, / Curve shows trip N setpoint for an 70 /

approxImateig \

25% flow reductton' i g

for three pump \

g operation 3 v

(283,860 gpm). 3

\

o !

The actual setpoint __

w l '. t be calculated --

3 PUMP \

$ ! by the Reactor --

EXAMPLE \' '

J i Pi>tectlon System 50 ;

b i _'and witt be directly 3

o proportional to the A actual flow with g three pumps.

i!

UNACCEPTABLE, UNACCEPTABLE-OPERATION OPERATION I '

30 20 ACCEPTABLE OPERATION FOR SPECIFIED RC

. PUMP COMBINATION in 6

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

20 25 30 35 40 15 -10 -5 0 5 10 15 40 -35 30 25 -20 Axial Power Imbalance, %

C-16

COLR Page 17 of 20

'

Revision 0 Table 1 OUADRANT POWER TILT Limits This Table is referred to by Technical Specification 3.2.4 Steady-state Steady-state Limit for Limit for THERMAL THERMAL Transient Maximum QUADRANT POWER TILT Limit Limit as measured by: POWER 5 60% POWER > 60%

(%) (%) (%) (%)

Symmetrical Incore 6.8 4.4 10.03 20.0 detector system Table 2 Necative Moderator Temperature coefficient Limit This Table is referred to by Technical Specification 3.1.1.3c ,

Negative Moderator Temperature -3.73 X 10" ak/k/*F Coefficient Limit (at RATED THERMAL POWER)

Table 3 Power to Melt Limits This Table is referred to by Technical Specification Bases B2.1 Batch 9A Batch 9D Batch 10B Batch 11 Batch 12 Fuel Assembly Type Mark-B8A Hark-B8A Mark-B8A Mark-B8B m rk-BION L Minimum linear heat rate to melt, kW/ft 20.5 20.5 20.5 22.3 22.3 C-17

y '

COLR Page 18 of 20 Revision 0 Table 4 Nuclear Heat Flux Hot Channel Factor - Fg This Table is referred to by Technical Specification 3.2.2 Heat Flux Hot Channel Factor F9 Fg shall be limited by the following relationships:

Fn $ LHR"(Bu) /[ LHR^VG *P] (for P 5 1.0)

LHR * *(Bu): See the Tables below LHR^W = 6.139 kW/ft for Mark-B8A fuel LHR^W =

6.253 kW/ft for Mark-B8B fuel LHR^W =

6.253 kW/ft for Mark-B10AZL fuel P = ratio of THERMAL POWER / RATED THERMAL POWER !

Bu = Fuel Burnup (mwd /mtU)

Batch 9A (Hark-B8A) LHR** kO/ f t Less than After Axial Seament 24,500 mwd /mtU 24,500 mwd /mtU 1 12.8 9.6 2 15.1 11.3 3 15.7 12.0 4 15.7 12.0 5 16.4 12.0 6 17.0 12.0 7 16.2 11.4 8 13.6 9.6 I

C-18 l

COLR s

Page 19 of 20

Revision 0 Tabic 4 continued Batches 9D and 108 (Mark-B8A) LHR ""* kW/ f t A

After Axial Seament 24,500 mwd /mtU 1 9.6 2 11.3 3 12.0 4 12.0 5 12.0 6 12.0 7 11.4 8 9.6 Batch 11B(Mark-B88) LHR A

""* kW/ft After 20,000 KWd/mtU Axial Seament 1 13.6

~

2 16.0 3 16.2 4 16.2 5 16.2 l

6 16.6 7 16.2 8 13.6 l

l Batch 12 (Mark-B10AZL) LHR CM"* kW/ft Less Than After l 20,000 mwd /mtU 20,000 mwd /mtU Axial seement 1 14.2 13.6 2 16.8 16.0 3 17.7 16.2 4 17.5 16.2 5 17.5 16.2 ~

6 17.8 16.6 7 17.4 16.2 8 14. 13.6 C-19

COLR Page 20 of 20 l Revision 0 Table S Nuclear Enthalov Rise Hot Channel Factor - F"u 1

1 This Table is referred to by Technical specification 3.2.3 Enthalov Rise Hot Channel Factor F"n F$u $ ARP (1 + 0.3 (1 - P/P ) ]

ARP = Allowable Radial Peak, see Figure P = THERMAL POWER / RATED THERMAL POWER and P $ 1.0 P, = 1.0 for 4-RCP operation P = 0.75 for 3-RCP operation Figure 7 Allowable Radial Peak for F$n i ii 2.! .

I i

I ..!

I 1 i i IJ F

l 1#\ ' ;

-~

Q-

_______,, _s ,.

E M.

i!

.,.'N

< 2.O f;1 -

.% s.,

m #t , r----N .- s'

'9.. g r,

,e[z.f] -,

'l'

-- ,,,m ,<

m e g

[

' mm' w - w

. . . I h, u X g

g ,9 .I 1 i i I 'M I

'9g a

'% ,. eI 7

II- -I I

I. .. ,I. . ., . ,

m, 1 ,,

's sA -N%

%i'b o

b ,_

t=x l 1

ss -

I.8 w ,

s, - s,cs.* 28.12,,m n .

m'bi '

x

'b 31'k' 1 I I

b 9&

5 g 6 ,. o ,,s is

' !FA-s N_ _

5634'"}

1.7 v ,

,o

_____g ' j i o

., x

. ___. i s 3

' ' ' ' '; N o ', '

l.6 ;

'-3 3 aug j* 8l4.36":

i. - ,

< i

'ita,w____

! 14 1

> ,i.1-er--

I.5 . . __ _a !.: !i. g

' ; i l . I12.48":

'I. .

T I i n 1

t i pp! ! 1.., .

1 : 1 1

' ' i

. , !!! 4-44+4-- ^

i

{

1.4 1.I l.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak

Based on an active core height of 140.6 inches. Linear interpolation and extrapolation above 112.48 inches are acceptable. For axial heigh *.s <28.12 inches, the value at 28.12 inches will be used.

C-20

I l

BAW-2223, Revision 1 October 1994

)I 1

l i

j I DAVIS-BESSE NUCLEAR POWER STATION '

UNIT 1, CYCLE 10 -- RELOAD REPORT i

!I ;

i s

e

I iI g .

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i

! B&W Fuel Company I

ML20149H140

Text

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