Text

Rev 1 to Davis-Besse Unit 1 Cycle 10 Colr
	ML20094R325
Person / Time
Site:	Davis Besse
Issue date:	11/27/1995
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20094R322	List: ML20094R319; ML20094R325;
References
	NUDOCS 9512040358
	Download: ML20094R325 (20)
	v • d • e

.,

COLR Page 1 of 20 Revision 1 l

5 I

TOLEDO EDISON COMPANY DAVIS-BESSE UNIT 1 CYCLE 10 CORE OPERATING LIMITS REPORT l

i I

LIST OF EFFECTIVE PAGES Page C-1 Rev. 1 l

t.

Page C-2, C-3 Rev. O Page C-4 through C-18 Rev. O Page C-19 Rev. 1 l

~Page C-20 Rev. O i

i 9512040358 951127 PDR ADOCK 05000346 A

.._,. PDR C-1

~. _.,

COLR 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 I

and Alarm Setpoints, O to 25 l

3.1.3.8

+10/-0 EFFD, Four RC Pumps l

3.1.3.6 Figure Ib Regulating Group Position j

and Alarm Setpoints, 25 +10/-0 3.1.3.8 to 460 t10 EFPD, Four RC I

Pumps i

3.1.3.6 Figure le Regulating Group Position I

and Alarm Setpoints, after 460 3.1.3.8 210 EFFD, Four RC Pumps 3.1.3.6 Figure 1d Regulating Group Position and Alarm Setpoints, O to 25 +10/

3.1.3.8

-0 EFPD, Three RC Pumps j

3.1.3.6 Figure le Regulating Group Position and Alarm Setpoints, 25 +10/-0 3.1.3.8 to 460 210 EFFD, Three RC Pumps 1

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 Rod Core Locations and Group Assignments l

3.1.3.9~

Figure 3 APSR Position Alarm Setpoints 3.2.1 Figure 4a AXIAL POWER IMBALANCE Alarm Setpoints, O EFPD to EOC, Four RC Pumps 3.2.1 Figure 4b AXIAL POVER IMBALANCE Alarm Setpoints, O EFPD to EOC, Three RC Pumps 2.1.2 Figure 5 AXIAL POVER IMBALANCE Protective Limits 2.2.1 Figure 6 Flux - o Flux /Flov (or Pover/

Imbalance /Flov) Trip Setpoints 3.2.4 Table 1 QUADRANT POVER TILT Limits 3.1.1.3c Table 2 Negative Moderator Temperature Coefficient Limit B2.1 Table 3 Power to Melt Limits C-2

j.

o.

COLR Pzga 3 of 20 Revision 0 3.2.2 Table 4 Nuclear Heat Flux Hot Channel l

Factor - F g 3.2.3 Table 5 NuclearEnthalpyRgseHot Channel Factor - F g 3.2.3 Figure 7 Allowable Radial Peak for F"M

~

l i

n t

l l

C-3

COLR Page 4 of 20 Revision 0 i

f TOLEDO EDISON DAVIS-BESSE UNIT 1 CYCLE 10 t

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 i

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 - 6 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) i

4) AXIAL POVER IMBALANCE Alarm Setpoints

5) AXIAL POWER IMBALANCE Protective Limits

6) Flux -o Flux /Flov (or Power / Imbalance /Flov) Trip Setpoints

7) OUADRANT POVER TILT limits

8) Negative Moderator Temperature Coefficient limit

9) Nuclear Heat Flux Hot Channel Factor, F and g

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 Fuel Assemblies."

C-4

COLK Page 5 of 20 Revision 0 F1gure l a' Regulatinq Group Position Alarm Setpoints

'O to 25+10/-O EFPD, Four RC Pumps --

Davis-Besse I,

Cycle 10 This Figure is referred to by Technical Specifications 3.l.3.6 ond 3.1.3.8

~t10 i

l POWER LEVEL F

r i

100 CUTOFF = 100%

l

/

n

-T l

l t

W 90 e

r f

l l

C..

l l

l 80 r

i k

UNACCEPTABLE

/

OPERATION r

70-

'i 2

Ik)PbtATION a

F

,/

RESTRICTED 60 f

o LU HARGIN

-~

s

-r

- e y

LIMIT 50 g

e a

e

+

e

40

/

s, f

.r a-c

/., ?

ACCEPTABLE OPERATION e

e o 30 rs-f L

CPERATION

E, lESTRICTED 4

c'. 20 m

1, e,

c' N

e t iO t-

[

fi s

e O"

O 25 50 75 i00 125 150 175 200 225 250 275 300 Rod Index (% Withdrawn)

O 75 100 l

I I

GROUP 5 0

25 75 i00 I

I I

i GROUP 6 0 25 100 1

I I

GROUP 7 sto la A Red 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-5

COLR i

Page 6 of 20 Revision 0 Group *l0 EFPD, Four RC PumpsAlarm Setpoints Position 25$utatinq Re FigureIb 10/-O fo 460 Davis-Besse I,

Cycle 10 This Figure is referred to by Technical Speelfications 3.l.3.6 and 3.l.3.8 l10 i

i I

i

{

~~-

POWER LEVEL

-r r

100 CUTOFF = 100% :.-

/

r 2 r

,,W l

l 90 e

r l

.r r

a_BO j

{

.r b

'i 70 2

W e

I

-rOPERATION m./ RESTRICTED P

Y 00 D

m

^~

~~

~

' hl MARGIN

-r-

>r

.s' Q

LIMIT

/

r-1 x 50 y

1 J'

ar r

r

* = -

2 3

49 j

y o

i

.r s-i r d',p OPERATION OPERATION

.eu 30 ra-

, nr s.

e E 20 i

s.

f e

a 5 l0 av

-e o

d' E

j O"

O 25 50 75.100 125 150 175 200 225 250 275 300 Rod Index (k Withdrawn)

O 75 100 l

l I

GROUP 5 0

25 75 i00 1

I I

I GROUP 6 0 25 100 1

1 1

GROUP 7 Neto la 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-6

4 COLR Pt e 7 of 20 Revision 0 Figure #$c R

ulotIng10 EFhD, Grou Position Alarm 5etpoints Af er 460 Four RC Pumps --

Davis-Besse I,

Cycle 10 This Figure is referred to by Technicot Specifications l

3.l.3.6 and 3.1.3.8 j

.IIO 4

POWER LEVEL J

l00 l

p_ CUTL" F = 100%

j f r

1

~ 2a 1

Q f'

141 90

./

/

i 6

1 G.

f~

BO l

l J

r r

_s l

g 70 OPERATION s

r 2

H

_ RESTRICTED 60 i

a j

j r

id MARGIN e

Q.

LIMIT t

50 i

e g

e

~

o r

,r w

40

/

-r

'i LMACCEPTABLE i

s c

ACCEPTABLE OPERATION i

e e

i OPERATION 1

e i

2 -"

. o 30 L

a ar f

e A

s 20

]

1 L

p e.

t 10 s

o

.e-J L

i O

O 25 50 75 iOO I25 I50 175 200 225 250 275 300 i

Rod Index (% Withdrawn) 4 0

75 100 I

I GROUP 5 0

25 75 100 l

I I

1 J

GROUP 6 O

25 100 I

I I

GROUP 7 Nato 1:

A Rod Group overlap of 25*5% between sectuen t l o t withdrawn groups 5 and 6, and 6 and 7 shall be maintained

.No.to 2:

Instrument error is accounted for in these setpoints.

C-7

m.

COLR Page 8 of 20 Revision 0 Figure 1d Requiatinq Group Position Atarm Setpoints O fo 25+10/-O EFPD, Three RC Pumps Davis-Bess. 1 Cycle 10 This Figure is referred to by Technical Specifications 3.l.3.6 and 3.1.3.8 IIO i

i00 C'y 90 0

Q.

80 d

M POWER t.EVEL

/

f

CUTOFT = 75%

r f

f F

r i

60

[

/

a tu UNACCEPTABLE F

OPERATION r

/

RATION f

RESTRICTED ;

'~ d

'~

40 z

3, 30 mg MARGIN y

/

i LIMIT-o ACCEPTABLE 5.

l8 r

/

Q.

i i

_m--Iv OPERATION e

i i

p

- 20

--- OPEFIATlON e

d" d

-9 RF:STRTCTFD min g

e A

s 10 t

a v

ar D.

ld

.O"'M O

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

O 75 100 l

l I

GROUP 5 O

25 75 i00 I

I I

I GROUP 6 0

25 100 l

l l

GROUP 7 Nato 1:

A Rod Group overtop of 25*5% between sociuent r al withdrawn groups 5 and 6, and 6 and 7, shall be maintained Nato 2:

Instrument error is accounted for in these setpoints.

C-8

COLR Page 9 of 20 Revision 0 F i g'u r e *1e Regulating Group Position Alarm Setpoints 25+10/-O to 460*l0 EFPD, Three RC Pumps Davis-Besse 1 Cycle 10 This Figur. is r.f.rr.d to by Technical Specifications 3.1.3.6 and 3.1.3.8 110 100 Ey 90 O

Q.

80 d

$$2: POWER LEVEL

/

z

CuTOrr = 7sx E 70

/

W r

u Z

r e

H d'

I 60

/

I a

W UNACCEPTABLE 6-OPERATION r

/

TION f

RESTRICTED ;

40 l

A l

~

m MARGIN s'

o 30 LIMIT

/

s L

f ACCEPTABLE OFERATION e

Q.

i 20 s-

, 1 s.

e a 10 o

e Q.

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 l

i I

I GROUP 6 0

25 100 l

l 1

GROUP 7 Note 1:

A Rod Group overlap of 25*5% between s o ciue n t i a t withdrawn groups 5 and 6, and 6 and 7 shalt be maintained Note 2:

Instrument error is accounted for in these setpoints.

C-9

COLR Page 10 of 20 Revision 0 Figure if Regulatinq Group Position A l a rm Se t p o i n t s *-

After 460f10 EFPD, Three RC Pumps Davis-Besse I,

Cycle 10 This Figure is referred to by Technical Speelfications 3.l.3.6 and 3.l.3.8 110 i

I i

1 lOO n

.T 2*

Q.

-.! 80 4

POWR LEVEL

((:: CUTOFF = 75%

//

T 70 l

l Y

/

l F

e

.r 60 l

l a

I LU UNACCEPTAlk E

/

H OPERATION f

O OPERATION

.fESTRICTED j

40 e

m

_f 7, 30 d"

MARGIN f

LIMIT u

ACCEPTABLE t-i

[

s OPERATION O 20 7

-s i

e I 10 4

o s

i 0.

1 0

O 25 50 75 i00 125 150 175 200 225 250 275'300 j

Rod Index (% Withdrawn)

O 75 100 l

I l

GROUP 5 0

25 75 100 l

i I

I GROUP 6 0 25 100 l

I I

GROUP 7 Noto la A Rod Group overlap of 25*S% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained Noto 2:

Instrument error is accounted for in these setpoints.

C-10

_ r

~.. _ _ _. _ _... _ _ _ _ _. _

COLR Page 11 of 20 Revision 0 Figure 2 Control Rod Core Locations and Group Aseignments Davls-Besse I,

Cycle 10 1

This Figure is referred to by Technical Specification 3.l.3.7 4

N I

A B

4 6

4

]

C 2

5 5

2 D

7 8

7 i

E 2

5 5

2 F

4 8

6 3

6 8

4 G

S 1

1 5

H H-6 7

3 4

3 7

6

-Y l

K 5

1 1

5 L

4 8

6 3

6 8

4

'I it 2

5 5

2 i

N l

7 8

7 0

l 2

5 5

2 P

l l

4 6

4 R

l l

l 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 C-11

COLR Page 12 of 20 Revision 0 Figure a APSR Position Alarm Setpoints This Figure is referred to by Technical specification 3..'.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 ooeration*

Insertion Prohibited per Tech Spec 3.1.3.9

Power restricted to 77% for 3 pump operation f

l C-12

COLR Page 13 of 20 Revision 0 Fl'gura 4a AXIAL POWER IMBALANCE Alarm Setpoints O EFPD to EOC, Four RC Pumps --

Davis-Besse 1 Cycle 10 This Figure is referred io by Technicot Specification 3.2.I 110 i

l l

OO-- - - ',

I T

n I

J 1

\\.

/

L 90 r

r n

s n

n i

e

-80 i

i i;

hCEP g-

-70 RESTRICTED g

REGION W

l A.

.s0 i

i 4

l Lt.

-50 l

5-

-40 u

i i

!._ 30 i

a i

i i

Y M

5 l PERMISSIBLE l

i vPERATING s

REGION

o i

i I

-40

-30

-20

-10 0

10 20 30 40 AXIAL POWER IMBALANCE %

LEGEND FULL INCORE

Based on measurement system EXCORE Note 1.

Instrument error is accounted for in these setpoints.

C-13

~ _ _ _ _ _ _. _.

COLR Page 14 of 20 Revision 0 Figure 4b AXIAL POWER IMBALANCE Alarm Setpoin1s O EFPD to EOC, Three RC Pumps Davis-Besse I,

Cycle 10 This Figure is referred to by Technical Specification 3.2.I 110 l00 90 80 1

i c

RESTRICTEC REGION

-- -70 RESTRICTED."_

t

/

?

FEGION r

r n

f f

J

._. 60 l

8

-50

,3o K---40 a

e a

o i

f f

U.--30 c

i

-20 l

l t

j PERMISSIBLE j

OPERATING i

REG"ON 10 i

s i

u u

2 l

-40

-30

-20

-10 O

10 20 30 40 AXIAL POWER IMBALANCE %

LEGEND

Based on measurement system EXCORE Nota 1:

Instrument error is accounted for in these setpoints.

I C-14

I l

COLR Page 15 of 20 Revision 0 l

< Figure 5 AXIAL POWER IMBALANCE Protective Limits l-l This Figur. le referred l

to by Technical Specification 2.1.2 l

% RATED THERMAL POWER 120 4 P W LIMIT (37.J9.I12)

(-37.09.I12)

--iiO

(-51.45.100),

_.ioo

,(55.21.96.06) 3 PUPF LIMIT 90 l

(-37.09.89.80)

(37.09.89.80)

. so (55.2I.73.06)

(-51.45.77.00) j

- 70 J

- 60

- 50 j

- 40 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION

. so i-20 l

ACCEPTABLE OPERATION I

FOR SPECIFIED RC i

PUMP COMBINATION

- 10 I

I I

t i

I I

I

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 AXIAL POWER IMBALANCE %

Required Measured Reactor Coolant Flow to Ensure Pumps Operatins Flow, spm Compliance, gpm 4

380.000 339.500 3

283.060 290.957 C-15

COLR Page 16 of 20 Revision 0 Figure 6.

Fl ux-- A Flux /Fl ow (or Power / Imbalance / Flow)

Trip Setpoints This Figure is referred 1o by Technical SpectfIcation 2.2.I I

ll1llI11 11lll111

\\

t

/

4 PUMP

\\

LIMIT

\\

s-im e

s j

T

\\

90

('N

' L 80 2

T N

.____2 Curve shows trip

/

setpoint for an N

\\

t M

f approximately 25.4 f l ow r e du c t i on x

g for three pump N

operation (283,860 qpm).

s

.M,

\\

The actuot setpoint will be calculated 3 PUMP o

J by the Reactor

- EXAMPLE 50 Protection System O

and will be directly 3

proportlenot to the o

A actual flow wlth g

three pumps.

UNACCEPTABLE-UNACCEPTABLE OPERATION OPERATION 30 20 ACCEPTABLE OPERATION FOR SPECIFIED RC PUMP COMBINATION 3o O

-40 35

_-30

-25

-20

-15

-10 5

0 5

to 15 20 25 30 35 40 Axial Power Imbalance, %

c

..~...

COLR Page 17 of 20 Revision 0 e

i j

Table 1 OUADRANT POWER TILT Limite This Table is referred to by Technical specification 3.2.4 j

i steady-state steady-state Limit for Limit for QUADRANT POWER TILT THERMAL THERMAL Transient Maximum as measured by:

POWER S 60%

POWER > 60%

Limit Limit

(%)

Symmetrical Incore 6.8 4.4 10.03 20.0 detector system I

1 I

Table 2 Necative Moderator T e rature Coefficient Limit 1

i

q This Table is referred r

J to by Technical specification

]

3.1.1.3c l

l Negative Moderator Temperature

-3.73 X 10 ak/);/*F d

i coefficient Limit (at RATED TIERNAL POWER)

Table 3 Power to Melt Limitt This Table is referred to by Technical specification Bases 52.1 j

Batch 9A Batch $2 Batch 10B Batch 11 Batch 12 Fuel Asswr.bly

~

Type

, Mark-BBA Mark-B8A Mark-B8A Mark-B8B Mark-B10ML l

Minimum linear heat rate to melt, kW/ft 20.5 20.5 20.5 22.3 22.3 1

C-17

2 COLR 1

Page 18 of 20 Revision 0

't Table 4 Nuclear Heat Flux Hot Channel Factor - F 9

This Table is referred to by Technical specification 3.2.2 1

J l

Heat Flux Hot Channel Factor F9 Fo shall be limited by the following relationships:

j Fg g LHR"( Bu ) / [ LHR*"

P ]

(for P $ 1.0)

LHR^32"(Bu):

See the Tables below LHR"" = 6.139 kW/ft for Mark-B8A fuel

)

l

. LHR"" = 6.253 kW/f t for Mark-888 fuel

]

AW LHR

= 6.253 kW/ft for Mark-B10AZL fuel 1

P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = Fuel Burnup (mwd /stU)

Batch 9A'fMark-B8A) LHR" kW/f t i

Tass than After Axial seament 24,500 mwd /stU 24,500 mwd /stU 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

i C -18

i as *'

COLR Page 19 of 20 I

Revision 1 t

Table 4, continued Batches 9D and 10B (Mark-B8A) LMR " kW/f'c After M fal Seoment 24,500 mwd /etU 1

9.6 2

11.3 3

12.0 4

12.0 5

12.0 6

12.0 7

11.4 8

9.6 r

i Batch 11B (Mark-B8B) LHR " kW/ft i

After Axial seament 20,000 mwd /mtU l

'l 12.9 2

15.3 3

16.2 4

16.2 5

16.2 6

16.6 7

16.2 8

13.6 i

Batch 12 (Mark-B10AEL) LHR " kW/ft Less Than After Axial Seoment 20,000 mwd /mtU 20,000 mwd /mtU 1

13.6 12.9 2

16.0 15.3 3

17.2 16.2 4

17.5-16.2 5

17.5 16.2 6

17.8 16.6 7

17.4 16.2 8

14.G 13.6 l

c_10

I COLR Page 20 of 20 Revision 0 Table 5 Nuclear Enthalov Rise Hot Channel Factor - F,"n This Table is referred to by Technical specification 3.2.3 Enthalov Rice Hot Channel Factor F"a F"n 5 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

~

2.1 1

1

,.m, D.

a.r Z

ll 2.0

- __,_~#.-- ;f;j 1.,_

m,_

i

f,+Qyy, m

m-m g ;.

g.

m

. g@+r;.,= ;

.x m

w

,g c

y e

1.9

-_t i

g a

w.

s a

s s

0 g

l*O y

'(

'N 29, 'g 2=y

,c.

' s.

r,w

'1, c

m-i u

' u s

i e

1.7 u.

56.24",

s

.0 s,'

c j

3:

w___-

I 'T o

1.6

-m

84.36"?

3 4

'-L i

l i?t.

l I5 2

l

- 1 12. ~ 8":

4

-H-+-

i 3 1 Y I

a f !

I I

i 1.4 l.1 1.2 1.3 1.4 1.5 1.6 f.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.

Foc axial heights <28.12 inches, the value at 28.12 inches will be used.

C-20

ML20094R325

Text

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