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

l LIST OF EFFECTIVE PAGES

t. Page C-1 Rev. 1 l 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 l 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 I

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 l and Alarm Setpoints, 25 +10/-0 3.1.3.8 to 460 210 EFFD, Three RC l 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 l 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 l

CORE OPERATING LIMITS REPORT ,

l 1.0 Core Operating Limits 1 This CORE OPERATING LIMITS REPORT for DB-1 Cycle 10 has been prepared in l 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) l 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, Fg 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 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 e

l l t W 90 r f l l C. . l l l 80 i

r k UNACCEPTABLE OPERATION r

/

70- 2 'i a

Ik)PbtATION F ,/ RESTRICTED o 60 -~

s f -r LU HARGIN - e y 50 LIMIT ,

g ; ; ,

e a -

+ e , e s, f

40 --

.r

/ a-

/

c e e

/- ., ? ACCEPTABLE OPERATION o 30 "

rs-L ----CPERATION ,f

E, lESTRICTED 4 c'. 20 _ ,,

m ,

1, e, c'

e N

t iO t-

[ s fie 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 FigureIb Re Position 25$utatinq 10/-O fo Group 460 *l0 EFPD, Four RC PumpsAlarm Setpoints --

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

{

100

~~-

POWER LEVEL :: -r r >

-- CUTOFF = 100% :.- / , r

,, :::::' < 2 r

W e l l 90 r

," l

.r r a_BO j {

< .r b 70 2 'i WI e

-rOPERATION P m./ RESTRICTED D 00

' hl m

MARGIN -r-

^~ ~~

>r

~

.s' Y

LIMIT ! / ,

Q x 50 y 1 J' ar r- 1

- =- 2 r 3 r o

49 j ,

y ,

i i .r s-OPERATION &

d',p &

.e r OPERATION u 30 , nr ra-

s. '

e , ;

E 20 ,,

i

s. 'f e a:

5 l0 av :

o d'

-e 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 Grou Position Alarm 5etpoints Af erulotIng10 460 EFhD, 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 p_ CUTL" F = 100% r l1 - ,

j a

f f'

~

1 Q 2 141 90 ./ /

i 6 / '

/

1 G. f~

J BO r

, l l r

_s s l g 70 '

- r OPERATION H

2

- _ RESTRICTED i a 60 ,

j r j

id MARGIN --" # e

Q. LIMIT t ,

g 50

, i , e e --

~

o r ,r w

40 >

-r

'i *-

c LMACCEPTABLE i /

e e s #

ACCEPTABLE e OPERATION i

-" OPERATION

. o 30 1 i 2 i <. -

L a ar sf e

A

]

- 20 1 L p#

e. ,

. t 10 s

o .e-L '

J ,,

i O

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

i 4

Rod Index (% Withdrawn) ,

0 75 100

! I I l GROUP 5 0 25 75 100 l I I 1 -

GROUP 6 J

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 I

i00 C'

y 90 0

Q.

80 -

d M POWER t.EVEL

/ r

CUTOFT = 75% ,

f

@ r f f F i a 60 tu UNACCEPTABLE -,-

[ /

F OPERATION r l

/ RATION

,,_ f RESTRICTED ;

' '~

40 z - d - l

" ' '~

mg ,

3, 30 MARGIN i y , /

o LIMIT- -

5. l8 r ' / "'- ACCEPTABLE e i p OPERATION Q. i i

i _m--Iv

- 20 --- OPEFIATlON e d"

g -9 RF:STRTCTFD min d

e s 10 t --

A :

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 E

y 90 O

Q.

80 d $$2: POWER LEVEL / ,/ """'

z ::::CuTOrr = 7sx ,

E W 70 r

/ u/

Z r e H d' I a 60 #

/ I W

6-UNACCEPTABLE ,

OPERATION r

/ TION

, f RESTRICTED ;

~

40 l "

A m ,

, l MARGIN s' " '

o 30 LIMIT / s L

e ,.#

f " - ACCEPTABLE OFERATION l Q. _--- i

- 20 , 1 s-

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 a 60 l l I

LU UNACCEPTAlk E /

H OPERATION f O OPERATION ,

.fESTRICTED

, , j

40

e m , _f

d" 7,

u 30 MARGIN LIMIT f -- '

' ACCEPTABLE l t-

s

- i [, OPERATION O 20 '

-s 7

,, i e I 10 o s -

4 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 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 l

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

COLR Page 11 of 20 Revision 0

' l 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 8 7 i

E 2 5 5 2 l F 4 8 6 3 6 8 4 l

G S 1 1 5 l

H H- 6 7 3 4 3 7 6 -Y l K 5 1 1 5

'I L 4 8 6 3 6 8 4 it i 2 5 5 2 ,

N l 7 8 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 l

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-- - - ' ,

n I T I

J 1 \.

r

/ r

., 90 L n

s > n n i e i

-80 i i; hCEP g- -70

-- RESTRICTED

, g ,

REGION

! W l

A. _

.s0 i @ i 4

l Lt . - -50 !

! ; l

! 5- -

-40 !

! u !

i

i a

!._ 30 i 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 # # t RESTRICTED."_

REGION --

-70

/ ,

,' ' ?

FEGION r r n f f J 60

' l 8 .

-50

,3 o .

! K---40 !

a .- e a o i f U.--30 f

! c !

> ; i l *- - -20 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

< Figure 5 AXIAL POWER IMBALANCE Protective Limits l

l-l This Figur. le referred l to by Technical Specification 2.1.2 l

% RATED THERMAL POWER 120 4 P W LIMIT

(-37.09.I12) (37.J9.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 l 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 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 t

' 11lll111 \

' / 4 PUMP LIMIT

\

im s- ,

se .,

j T

\ .__

90

('N 80

,- L ' T 2 %_

/ .____2 Curve shows trip N N

-.' setpoint for an \ t M f approximately ,

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

N for three pump '

@ operation ' '

.M, " (283,860 qpm). s

\

o The actuot setpoint __

will be calculated --

3 PUMP %

$ by the Reactor EXAMPLE J 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

0 5 to 15 20 25 30 35 40

-40 35 _-30 -25 -20 -15 -10 5 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 I detector system I 1

I Table 2 Necative Moderator T e rature Coefficient Limit 1

i

q l This Table is referred r J to by Technical specification ]

3.1.1.3c l

l Negative Moderator Temperature -3.73 X 10 dak/);/*F i

coefficient Limit (at RATED TIERNAL POWER)

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

l Batch 9A Batch $2 Batch 10B Batch 11 Batch 12 i Fuel Asswr.bly Type Mark-B8A Mark-B8B

~

, Mark-BBA Mark-B8A Mark-B10ML l Minimum linear

': heat rate to melt, kW/ft 20.5 20.5 20.5 22.3 22.3 1

l C-17

'1 2

COLR

1 Page 18 of 20 Revision 0

't ..

Table 4 Nuclear Heat Flux Hot Channel Factor - F9 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 ]

LHR AW = 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

l 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 l 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 __,_~#.-- ;f;j# ll 2.0 1.,_ ; i m,_

m .< - m

. ::::;f,+Qyy, g ;.

m- --. _

g. . , m ,,

.x ::

.- g@+r;.,= ;

m

% w ,g c

e 1.9 y-_t .

-;;__. -,." ,.' ,_' l g a '

-' w. ,-

s i-a s 0 ,

s ,

g y l*O '( '

'N '

,c . 29, 'g 2=y c s.,, r, w .

'1, ,

m-i u , '%. ---

u - .

, , s, e 1.7 .

,.. u. ', i s ' '

-,.' ,.-

56.24", ' '

.0 ,,

s,' ;

c '-

'- , j 3: ; ,, w___-

o 1.6

-m I 'T

84.36"?

--, 3 ;

4 i

'-L l i?t .

I5 .

2 l -

l - 1 12. ~ 4 8":

-H-+-3 1 Y i

I a

f ! I I 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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