Text

Revised Proposed Tech Specs,Reflecting Editorial Changes to 890616 Application for Amend to License NPF-3 Concerning Relocation of cycle-specific Core Operating Limits from Tech Specs to Core Operating Limits Rept
	ML20246C528
Person / Time
Site:	Davis Besse
Issue date:	08/21/1989
From:	; TOLEDO EDISON CO.
To:	;
Shared Package
ML20246C520	List: ML20246C518; ML20246C528;
References
	NUDOCS 8908250008
	Download: ML20246C528 (40)
	v • d • e

___ - _

f; 5

j s Docht Numbar 50-346

Licen;3 Nu:ber NPF-3 l ' Serial Number 1691 i Attachment 2 Page'1

. INDEX DEFINITIONS SECTION

,PAGE 1.0 DEFINITIONS (Continued)

SOLI DI FI CATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6a OFFSITE DOSE CALCULATION MANUAL (0DCM) . . . . . . . . . . . . . . . . 1-6a GASEQUS RADWASTE TREATMENT SYSTEM. . . . . . . . . . . . . . . . . . . . . 1-6a VENTILATION EXHAUST TREATMENT SYSTEM. . . . . . . . . . . . . . . . . . 1-6a P URGE- PURGI N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 6b-VENTING............................................... 1-6b HEMBER(S ) 0F THE PUBLI C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6b

$_ITE B00HDARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6b UnRESTRI CTED AREA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6b rDEWATER I N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1.-6b OPERATIONAL MODES (TABLE 1.1)......................... 1-7 FREQUENCY NOTATION (TABLE 1.2)........................ 1-8 CoREOPERAWG L,ggis Report l-(o c r

DAVIS-BESSE, UNIT 1 la Amendment No. ES 8908250008 890821 PDR ADOCK 05000346 P PDC

.. - _ _ _ _ _ _ _ - _ _ - _ - _ - - - _ _ _ - - l

n ,,

y k : ?'

... -q Ddeket'Nubber50-346-

.. License Number NPF-3 Serial Number 1691-Attachment 2

!" Page 2' DEFINITIONS-p --r w n <- v w .-- _ _ ,

CORE OPERATtMG btHtTslE? ORT ,

I y i. 4 l. % Cone 0PERATiws LiuiT,Teloar is tL, 6;t- sp,cct, l( docam,s4. 4Lat puvides core 1;.its pr Acurr,,1 y operab

,,,;fs shatt reload ogcle.he cgcle spcific cor< opeut6,3 It t be determinea {or eact, reloaa eqcte in accoraare, win

[ 3pci(-kation (o.9.1.7.7 tant oputiew withia Rese core c>perativgi limits is address,d in insMJual s pecif'cabu,

% .' m "

1 DAVIS-BESSE, UNIT 1 -

c

)

'4 Docket. Number 50-346

Licen;a Number NPF-3

.' n ADDITIONAL CHANGES l'REVIOUSLY Page 3 PROPUSE0 6Y LETTER -

Serial No. 1407 Date H/1/87 REACTIVITY CONTROL SYSTEMS ACTION _: ' (Continued) c) A power distribution mgp is obtained from the incore detectors ani F and F are their limits wikhin 72Nours. verified to be within '

d) Either the THERMAL POWER level is reduced to < 60%

of the THERMAL POWER allowable for the reactor _

coolant pump combination within one hour-and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Flux Trip Setpoint is reduced to < 70% of the THERMAC POWER allowable for the reactor coolant pump combination, or e) The remainder of the rods in the group with the inoperable rod are aligned to within + 6.5% of the _

ino erable rod within ne hour while_maintai_ning the

. . . . . , . . n,.. 4 . .a - -i.- 'i4 i

E E5I5 T 5 :. U .l T 5e ail E5CiON ]- e ER Tevel sha e res ricted pursuant to Specification 3.1.3.6 during subsequent operation.

posiHon o( b rods minta N Nih pwve N Greg.Ng blhR, ped.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each control rod shall be detennined to be within the group average height limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Asyninetric Rod Fault Circuitry is inoperable, then verify the indi-vidual rod position (s) of the rod (s), with inoperable Faul Circuitry at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1. 3.1. 2 Each control rod not fully inserted shall be determined to be OPERABLE by movement of at least 2% in any one direction at least once every 31 days.

I i

DAVIS-BESSE, UNIT 1 3/4 1-20 l

. l Dockpt Number 50-346

,- Licen;6 Number NPF-3

-Serial Number 1691 Attachment 2 Page 4 REAL.uvm CONTROL SYSTEMS RECULATING ROD INSERTION LIMIT {

LIMITING CONDITION FOR OPERATION 3.1.

12:;;;1 : : The regulatinth shall bs[liai;;d i ;J., . im- 1 m

g_;u; er--1 ;

Mfri d. Tig=:: 3.1 C.---J -2L, 3.1-Oe, 1 f -25. f. red L g;;;;; 5, i > 7. pri bian ed witW, A s<-cep* L.i...

.. blee

. ;i 1f ai;hd;.- 4 he __;;;a;=

25;5! ;E2'1

~ reat4:ati sg rod positio providea i, ti.. CoRECPETATildG ltRtT**o pe r.+i ,. G its p A : MD ES 1* and 2*t. RT.

ACTION Vith the regulating rod groups inserted beyond the coper SS .

l limits (in aorregion sequence overlap other thanthe outside acce table _ operation), or with any group Aiairp except for l surveillance testing pursuant to Snacif f em td an9 1 J. L 2- ei th=rt

a. fprovia,Ji,, & Cotrome Restore the regulating groups"IEvithin tila Ta_Ation tikrrsh)etiYs"YTTin~2 Of l

'povW,a ta,00RCCPERAnkbht s Thfter

b. m .< w Reduce THERMAL POVER to less than or equal to that fraction of_ RATED F which ithin 2ishours, allowed or by the rod group positio@.i; thO c.

gg,;g, p igg,'

Be in at least HOT STANDBT vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I'" t*"

NOTE:

If in unacceptable region, also see Section 3/4.1.1.1.

See Special Test Except2on 3.10.1 and 3.10.2.

4With k eff > 1.0.

DAVIS-BESSE, UNIT 1 3/4 1-26 Amendment No. 11, 33, 41, 42, 45, 61, 69, 80,123

m . . . . .

1

- ,DEckat Number 50-346. ,

L

)l'M, ,- Lic:nsa Nurber NPF-3 l Serial Number 1691 l~ Attachment 2

-Page 5;

' REACTIVITY CONTROL-SYSTEMS REGULATING ROD INSERTION LIMITS SURVEILLANCE REQUIREMENTS

. y , . . . . . .

t=ws i.s., Coascreemus tmin Tr*=v

- w~

4.1.3.6 The 11 be determined to be, within theM:itjer phosy r ion m "--_;coeach art ; gregula_tingrou

r. m li t least once every-12-hours except when: --

a. The regulating rod insertion limit alarm is inoperable.'then verify the groups to be within the insertion limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ;

b. The control rod drive sequence alarm is inoperable, then verify the groups to be within the sequence and overlap limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b

..j'

+

DAVIS ,BESSE. UNIT 1 3/4127

' Doc et Nu:.ber 50-346--

4- ' ^Licenna Number NPF-3 Serial Number 1691 Attachment 2 Page 6

\ Figure 3.1-2a Regulating Group Position Limits, 0 to 325 10 EFPD, Four RC Pumps --

/

Davis-Besse 1, Cycle 6

./

/

(300.1021-(258,102) ,

3 100 -- P r Level (270,102)

Cuthf=100%

'(270,92)

SHUTDOWN 2 MARGIN 80 -

' (250,80)

LIMIT j

a ,

b /

w UNACCEPTABLE

/

i: OPERATION 60 - OPERATION g RESTRICTED (180,50) o

$ 40 -

E E

{ (128,28. )

i 2 20 -

/

ACCEPTABLE PERATION 4 (0.0,5.0) 0 ' ' '

O 100 200 300 Rod Index (*. Withdrawn)

GR 5 i- ' '

O 75 100 GR 6 i e * '

, 0 25 75 100

' GR 7 ' ' \'

O 25 10

/

DAVIS-BESSE, UNIT 1 3/4 1-28 Amendment No. 11, 33, 45, 61, 80, 123 \,

k,. _mm______ _ _ _ _ _ _ _ - - - -

l .

e, , Docket Nuzber 50-346 / )

.' s Licens:a Nurb r NPF-3.

Serial Number-1691-Attachment 2 Page 7

\ Figure 3.1-2b Regulating Group Postion Limits After -

f N. 3251 10 EFPD, Four RC pumps, APSRs Withdrawn -- Davis-Besse 1, Cycle 6 (266,102 (300,102) e -

100 -

Power Level '(270,102)-

Cutoff = 100%

SHUTDOWN 70,92)

MARGIN 80 . l.IMIT N (250.80)

=

s g N

! OPERATION 5 60 - '

' UNACCEPTABLE

$ OPERATION f

o (17 .50)

(180.50) j 40 -

O E

u (136M8.5)

I e 20 -

ACCEPTABLE OPERATION i (0.0,5.0 0 -- ' ' '

O 100 200 300 Rod Index (% Withdrawn) \ \

GR 5 ' ' '

O- 75 100 GR 6 i ' ' '

O 25 75 100 GR 7 ' ' '

O 25 100 DAVIS-BESSE, UNIT I 3/4 1-28a Amendment No. 11, 33, 42, 45, 61, 80, 123

__m- .__ _____.__..__-__....____.._m__

<x N., Docket Number.

Liernsa Number NPF-3 50-346

. Serial Number 1691 Attachment 2 Page 8 Figure 3.1-3a Regulating Group Position Limits, j 0 to 325i 10 EFPD, Three RC Pumps --

Davis-Besse 1, Cycle 6 100 -

$g 80 - f 58,77) (300,77) e s I SHUTDOWN h MARGIN e(270,69.5)

$ LIMIT $

5 60 -

)[ (250,60.5) e

.d c

I UNACCEPTABLE OPERATION h L OPERATION RESTRICTED y 40 -

(17 )

y 180,38) h g*0 4 -

(128,21.8) ACCEPTABLE

/ OPERATION 0 > ' ' '

O 100 200 300 Rod Index (% Withdrawn)

GR 5 ' -

O 75 100 GR 6 i ' ' '

25 75 100 O

GR 7 ' ' \'

0 25 100

\

DAVIS-EESSE, UNIT 1 3/4 1-29 Amendment No. 11, 33, 41, 45, 61, 80, 123

Dock:,t.Nu ber 50-346 Lice'ns3 Nu:ber NPF-3 '

_ 4

Serial ~ Number 1691-C Attachwient 2' y Page 9

[ Figure 3.1-3b - Regulating Group Position Limits L

After 325 10 EFPD, Three RC Pumps, APSRs Withdrawn -- Davis-Besse 1, Cycl 6 __ '

100 - '

2 80 -

(266,77) (300,77)

.\

[

c.

\, SHUTDOWN / 5 0 sansin (270,77) f g UNACCEPTABLE LIMIT

= OPERATION (270,69.5) 0 -

\

\ 250,60.5)

. S \

E

" \

OPERATION 40 -

x17 .38) RESTRICTED E (180,38) t' E

I

! 20 - N (136,21.8)

=.

O'

[#

CCEPTABLE ERATION 0 / 100 200 300 Rod Index (% Withdrawn) \

GR 5 ' ' '

O 75 100 GR 6 i ' ' '

0 es /c 100 m GR 7 ' .

O 25 (00 j

\

\s

\

DAVIS-BESSE, UNIT 1 3/4 1-29a Amendment No. 11, 33, 42, 3 45, 61, 80,123

.s__________-_-_---------

W ,

^

.y G v

,, Docket Number 50-346

+: - ' tl Liernsa Number'NPF-3:

r-e" !f Serial Number 1691 '

. Attachment 2 Page 10-

.i REACTIVITY CONTROL SYSTEMS-ROD PROGRAM LIMITING CONDITION FOR OPERATION

l asse JH l us 1 3.1.3.7 Each control r A safety /,. oc u ating and APSR) shall be pro r y operate in the_ ore 4+4enjand rod group specified in b isus a s. T-4. O[b5pE RATIur. El HITI YEPoRT .

=-

)

3 APPLICABILITY: MODES 1* and 2*.

1 ACTION a sse h With any control r rogramad to operate as specified above, bel.in-HOT STANDBY within hour.

SURVEILLANCE REQUIREMENTS 4.1.3.7 asw d 's j a. Each control r a be demonstrated to be progransned to l operate in the specified core Wand rod group by:-

1.

b Selection and actuation from the control room and verifi-cation ~ of movement of the proper rod as indicated by both the absolute and relativt position indicators:

EekWe a) For all control r er e control red drive patches are locked bsequent to test, reprogramming or maintenance within the panels. -

c

-Gis,e Mes b) For specifically affected individual roc following maintenance, test, reconnection or modii ation of power or instrumentation cables from the control rod drive control system to the control rod drive.

2. Verifying that each cable that has been disconnected has been properly matched and reconnected to the specified control rod drive.

b. At least once each 7 days, verify that the control rod drive patch panels are locked.

l '

L

See special Test Exceptions 3.10.1 and 3.10.2.

l DAVIS-BESSE UNIT 1 3/4 1-30 Amendment No.ll )

l

._____ _ _ a

' 1

x

, j

.. pockat Nurber.50-346L

~'

. .: . ... Licenso Nuah2r NPF-3

Serial Number 1691 Figure 3.1-4 Control Rod Core Locations ,

Attachment 2 and Group Assignments -- ;

Page 11 D yJs-Besse 1, Cycle 6 :l N

'\ 1 A \

5 \ 4 0 4 C \ 2 5, 5 2 l

D

\ 7 8 7 8 7 / _i E \ 2 5 5 J

/

F 4 \ 8 6 3 6 8/ 4 G 5 \ 1 1 l

/ 5I H w -- 6 7 N- 3 4 3V 7 6 -Y

\

K 5 1 1 / 5 L 4 8 h 3 / 6 8 4 M , 2 5' \ j 5 2 N l 7 8 g 8 7.

~

_0 l 2 / \5 2 P l l l f 6 \ 4 R I i/ \

l b .

1 2 3' 4 5 6 7 8 9 10 11 13 14 15

/ Group No. of Reds Fun \

ction

/

/ 1 2

4 8

safet'ys Safety' 3 4 Safety X , Group Number 4 9 Safety x 5 12 control \

/ 6 8 Control '

/ 7 8 Control \

/ 8 8 APSRs Total 61

\

/

\

DAVIS-BESSE, UNIT 1 3/4 1-31 Amendment No. 11,33,45\,

61, 80, 123 \

r- ~

L . .' -

L A

- Docket Number 50-346-

?'- License Number NPF-3

' Serial Number 16911 Attachment 2

., 4 Page 12

~

REACTIVITY CONTROL SYSTEMS XENON REACTIVITY LIMITING CONDITION FOR OPERATION 3.1.3.8' TH R shali not be increased above the power level cutoff specified i Ti ;rc :.b:7g cc nn. nf the followina conditions is l satisfied: Q;gf<g yg g g g- sgeg j hes 64Tous..J7 a, Xenon reacIivity is within IOleM he equilibrium value for RATED THERMAL POWER and is approaching stability, or

b. THERMAL POWER has been within a range of 87 to 92 percent of RATED THERMAL F0WER for a period exceeding 2-hours in the soluble poison control mode, excluding xenon free start-ups.

APPLICA8ILITY: MODE 1.

ACTION:-

With the requirements of the above specification not satisfied, reduce THERMAL POWER to less than or equal to the powr level cutoff within 15 minutes.

SURVEILLANCE REQUIREMENTS 4.1. 3. 8 Xenon reactivity shall be determined to be within 10% of the equilibrium value for RATED THERMAL POWER and to be approaching stability or it shall be detemined that the THERMAL POWER has been in the range of 87 to 92% of RATED THERMAL POWER for > 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , prior to increasing THERMAL POWER above the power level cutoff.

DAVIS-BESSE, UNIT 1 3/4 1-33

_ _ . _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _a

1 1.-

H ' * '

Docket Nu;ber 50-346 /

.. Lid:ns3' Number NPF f~ Seriel Nu;ber 1691 i

' Attachment 2' 'J Page 13 REAvuvm CONTROL STSTEMS AYTAL POVER SHAPING R0D INSERTION LIMITS LinAumi CONDITION FOR OPERATION 3.1.3.9 The axial r995.~ power shaping rod group shall3Cbell'r' -

eda in #4:1- '

in:x:'.h limits exial pas.eer shetind. .*id .ee 3.1--3;, J5t,,1

',J = OW(M

'i., , CORE CPER lAfstJC&<

rod osition, r paip- BMlfs REPt aue pra t

APPL 6 : MODES 1 and 2*.

~

~ '

-~

ACTION Vith the axial power shaping rod group outside the above insertion limits, either:

a. Restore the axial power shaping rod group to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

b. Reduce THERMAL POVER to less than or equal to that fraction of RATED THERMAL POVER vhich is allowed by the rod group position using the c lejp thi pNeb [s aY[i o

c. Be in' l ST

~

SURVEILLANCE REQUIREMEffrS

.rroSSOke *E O h "GN!_* b Y 4.1.3.9 The position of the _ a_ foverTshaping rod group shall be determined to be within th "-~rstlBlimitsAat least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when the axial power s aping rod insertion _ limit alara is l' inoperable, at least onn then qveryverify the group to be within the@g;dibQlimi_

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . _

l

'F*WdsJii%,SpE @ m Lun srs Rspow i

Vi th K,gf >,1.0.

DAVIS-BESSE, UNIT 1. 3/4 1-34 Amendment No. 33, 42, 45, 61. 69.

80,123

, b < Docket' Number 50-346

. License Number NPF-3 L Serial Number 1691 , j Attachment 2 .j 1

Page 14 Figure 3.1-Sa APSR Position Limits, O to 325 10 EFFD, Four RC._P. umps -- Davis-Besse 1, Cycle 6 3ELETEbl t

RESTRICTED REGION 100 (0,102) (100,102) 80 -

2 w

3 m.

J

h. 60 -

P RMISSIBLE a 0 RATING REGION U

n o 40 -

T 8

5 \

S.

'b g 20 -

s.

/

0 10 20 30 40 50 60 70 8 90 100 APSR Position (*. Withdrawn)

/

/.

DAVIS-BESSE, UNIT 1 3/4 1-35

/ Amendment No. 33, 45, 61, 80,123

,7

. s" :

. ' Deck;t' Number 50-346-

' 'T \,

' License'Ausber NPF-3

' Serial Number 1691

' Attachment 2 3.0 Page 15 Figure 3.1-5b APSR Position Limits After N 325 10 EFPD, Three or four RC

' Pumps, APSRs Withdrawn --

100

/

l

'E 80 -

a.

I W 60 - APSR I ,ERTION. OT ALLOWED E IN THIS TI INTERVAL S \

a

~ % ' 40 -

Y 20 -

[

o 3

c 0 ' ' ' ' ' ' ' ' '

O 10 20 30 40 50 60 70 30 NO 100 APSR Posit 2cn (*. Withdrawn) l~

l j DAVIS-BESSE, UNIT 1 3/4 1-36 Amendment No. 33, 42, 45, 61, 80,123

.- l

( a- DorJtet Number 50-346

!: .L- 'Lican'se Number NPF ) Serial Number 1691- l

[ ' Attachment 2 !

'Page 16 Figure 3.1-Sc APSR Position Limits, O to 325t 10 EFPD, l Three RC Pumps -- Davis-Eesse 1, Cycle 6 '

DE ETEh

/

,- v

/ '

/

/ l

/

100

/ l B0 I RESTRICTED REGION E -

0 g

'(0.77) / (100,77)

a. . \ !

==l 1

-k )

W 60 i

S 2

a 1 b 1 o 1 5

LO -

/

l PE M S$1BLE OPERATING REGION

\

l t / i fi / ^

e !

3 i

- 20 -

9 , , , , , . , ' ' ' !.

i 10 20 30 40 50 60 70 80 \ 90 ;00 l APSR Position (* Withcrawn) l

/

l.

DAVIS-EESSE, UNIT 1 3/4 1-37 Amendment No. 33, I.S. 61 69, 80,123

_ - _ _ _ _ _ . . - _ s

1 Donket I'u ber 50-346

.~

Licen2 Number NPF-3 Serial Number 1691-Attachment 2

- Page 17 3/4.2 POWER DISTRIBUTION LIMITS AIIAL POVER IMBA1ANCE LIMITING CONDITION FOR OPERATION 3,2d AKIAL POWER I"**' ^7 *k-11 ha ==4=tm4 w thg[b e64e-ehoum vithi it

{kpmv;44 F8 io-U; 3.IllCPEcAT8MG ne CoeE 12 2. LJNTS SCC'P *E,MTblE

~

y- AMAt ?p4GR IMBALAQth operdiny b I

z APPLICABIi.ITf: MON 1 a'bove 40% of Rt.TED TREEM&L POVER.*

ACTION Vith AIIAL POVER IMBALANCE exceeding the limits specified above, either:

a. Restore the AIIAL POWER IMRALANCE to vithin limitaqrithin 5 sinutes, or l twe. i.% Coat ., 6Wiatica

,_ - - Likits - - Rteoet b.

Vithin one hour reduce power until abalance limitge_ met or to _

40% of RATED THERMAL POWER or lessa ~ Jiasini. o,eremtAtisq t:6nsiNG gv==

suRvEn.tANcE REovIREuRNTs 4.2.1.

The AIIAL POWER IMBA1ANCE shall be determined to be vidiiith 14=it*=t least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 40E of RATED TRERNAL jFruv_em calculate

_exe pt when the Arrit POWER IMBALANCE alarm is inoperable, then the AZIAL POVER IMBALANCE at least once per hour.

( ,7 ..

tPVM41 in kle (OREOPERKH4 kWinhAT ws_v l

See special Iest Exception 3.10.1.

t DAVIS-EESSE, UNIT 1 3/4 2-1 Amendment No. 33.

42, 45, 61, 69.

80, 113

+

.,, Docket Number'50-346 Li' cense Number NPF-3

Serial Number 1691'

\. Attachment ' Page 18 2 Figure 3.2-1 AXIAL POWER IMBALANCE Limits, Four RC Pumps -- Davis-Sesse 1,

--110

(-20,102) (15,102)

"100

(-25,92)

. . 90 < (15,J2)

\ s E

(-28,80),

g. . go /(20,80) 3

- - 70

- .60 S

(-28,50) 0 a (20,50) 3 50

\40s

\

RESTRICTED PERMISSI EE -

- 30 s REGION \

OPERATJ4G $. x REG N \

'o -

- 20 x c

- 10

, , ,o , , , < , e '

-50 -40 30 -20 -10 0 10 2O 3h 40 50 AXIAL POWER IMBALANCE (%)

l l

l I

DAVIS-BF.SSE, UNIT 1 3/4 2-2 Amendment No. 11, 33, 45, 61, 60, 123

(:- * '

~

'#. . D6cket Number 50-346

\. License Number NPF-3

-Serial Number 1691 Attacht2nt 2 /

Page 19 j/

o

.\- Figure 3.2-2 AXIAL POWER IMBALANCE Limits, Three RC Pumps -- Davis-Besse 1,

/

! g\ . . ,/

cle 6

)ELETE.h. j!

\ /

. 110 j/ .

/

100 /

90

/

- - 80

(-15,77)- ,, ( 11'.25,77)-

(-18.75,69.5) . 70 i

/(11.25,69.5)

E

(-21,60.5)' i - -6 i(15,60.5) a l ss .

3fg50 w/

(-21.38) o j /:g- .\O g o (15.38)

/ "' ;": \

/ t-- 30y 1 \

RESTRICTED / s REGION y

[ t" 20 ,gg !

5 ga

- 10 h

c. U

. , r ra , , _ ,

-50 -40 '30 -20 -10 0 10 20 3 40 50 AXIAL POWER IMBALANCE (%.'

\

6 DAVIS-EESSE, ISTIT 1 3/4 2-3 Amendment No. 11, 33, 45, N )

61, 80, 123 j j

Dockst Nurber 50-346

- 1:icen02 Nurber NPF-3 .

Serial Number 1691 Attachment 2 Page 20 I

P07ER DISTRIBUTION LIMITS OUADRANT POVER TILT LIMITING CONDITION FOR OPERATION BAhQJQWR TTf Tfm11 no_t eretackth3_Slandy_ State -Limit _

-ef Tale 3.2-1. & Q chuhuT t'oG U- LT p m Wed m We ch!E OLxWW4 -

\

a MirA <2&oom . y-- - --

AP I DDE 1 above 15% of RATED THERMAL POVER.*

ACTION:

a. Vith the OUADRANT POUER TILT determined to exceed the Stea.d b '

S,tAla_ Q R but less than or equal 3Jhe Transien_t_Li_m_i_t{-ef-RATNG LtMGS REPerr: j

1. Vithin 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

a) Either reduce the QUADRANT POVER TILT to within its Steady State Limit, or b) Reduce THERMAL POVER so as not to exceed TEERMAL POVER, including porer level cutoff, allovable for the reactor coolant pump combination less at least 2%

Pr each 1% of OUADRANT POVER TILT in excess of the Steady State Limit and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the High Flux Trip Setpoint and the Flux-A Flux-Flow Trip Setpoint at least 2% for each 1% of QUADRANT POVER TILT in excess of tho Steady State Limit.

2. Verify that the QUADRANT POVER TILT is within its Steady State Limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter exceeding the Steady State Limit or reduce THERMAL POVER to less than 60*. of THERMAL POVER allovable for the reactor coolant pump combination within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the High Flux Trip Setpoint to < 65.5% of THERMAL POVER allovable for the reactor coolant pump combination within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POVER; subsequent POVER OPERATION above 60% of THERMAL POVER allovable for the reactor coolant pump combination may proceed provided that the OUADRANT POVER TILT is verified within its Steady 3 tate Limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED THERMAL POVER.

i

See Special Test Exception 3.10.1 DAVIS-BESSE, UNIT 1 3/4 2-9 Amendment No.123

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

3-

, t ' Docket Number 50-346 b;+ - Licend2 Noaber NPF-3

-+ serial Number 1691- ,

A00ifiONAL CHANGES PREV 100SLV I

!Attacament 2 iPage 21 ' PROPOSED SY LETTER SerialNo. /401 . Date ///2 /o7 POVER DISTRIBUTION' LIMITS

' LIMITING CONDITION FOR OPERATION (Continued) b.

Vith the OUADRANT POVER TILT determined o exc ed the Transient-Limit.but less of misalignment thsn the aMaximum either safety, regulati Limit d P M J W due to 'l ishaping rod - prJar oover_

Povdadi., w caer

- opuATN4 UMIT*1 revert 1.. Reduce THERMAL POVER at least 2%' for eachi% [indicat

-~

OUADRANT POVER TILT in excess of the Steady State Limit within.30 minutes.

-* 2.

Verify that the QUADRANT POVER TILT 'is vithin its Transient'Liait vithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the.

Transient Limit.or reduce THERMAL POVER to less than 60%

, of THERMAL POWER ' allowable for the reactor coolant pump combination within the next 2. hours and reduce the High Flux Trip setpoint to < 65.5% of THERMAL POVER allowable for the reactor coolant pump combination' within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3. -Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER;. subsequent POVER OPERATION above 60% of THERMAL POVEE allowable for the reactor coolant pump combination may proceed provided~

that the OUADRANT POWER TILT is verified within its Steady State Limit at least once per hour for-12 hours or until verified acceptable at 95% or greater RATED THERMAL POVER.

c. With the OUADRANT POVER TILT determin to -the Transient Limit but less than the Maximus Limit . . __ _; 2 . . - ., due to causes other than the misalignment o safarv.0 m 1E - '" #

ing or axial power shaping rod: 9d [#

1. Reduce THERMAL POWER to less than 60% of THERMAL POVER alloweble for the reactor coolant pump combination within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the High Flux Trip Setpont to ,< 65.5% ,

of THERMAL POVER allowable for the reactor coolant pump combination within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2. . Identify and correct the cause of the out of IJait condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 60% of THERMAL POVER allovable for the reactor coolant pump combination may proceed provided that the QUADRANT POVER TILT is verified within its Steady State Limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER.

DAVIS-BESSE, UNIT 1 3/4 2-10 Amendment No.123

Docket Number 50-346

.. Licen:2 Number NPF-3 Serial Number 1691 Attachsent 2 Page 22 POVER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: - (Continued')

d. With t Limit _.-.....u VER TILT determined to exceed the Maximus reduce THERMAL POVER to < 15% of RATED l

[

}fff{3LLANCEREQUIREMENTS r.,a.

- - m

_ The QUADRANT POVER TILT shall be determined to be s-tu$wtv Side-) ,

t least once every 7 days during operation above ~

of RATED i I'r 4: 's y POVER except when the QUADRANT POVER TILT alara is inoperable, han ours.the OUADRANT POVER TILT shall be calculated at least once per 12 pvideA i% the CeW OERAt06 li.4:Ts Tcpon DAVIS-BESSE, UNIT 1 1 3/4 2-11 Amendment No.123

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1 - ,j* Dockh'tNumber'50-346:

' ~'- .Licensi Number NPF-3 Siri:1 Number 1691

? Attachment 2

- Page 24 13 /4'. 2. POWER DISTRIBUTION LDiITS l'

BASES lI The specifications of this section provida assurance of fuel integrity during t

Condition I- (normal operation). and II (incidents of modarate frequency) events by:

I' . (a) maintaining the minimus DN3R in the core 21.30 during normal opera-density 1during short term transients. . (b) maintaining the peak-linea ~r power tion'and 18.4 kW/ft during normal operation, and (c) maintaining the pealt poweridensity less than the 11mics given in the bases to specification 2.1 during short term transients. In addition, the above criteria must be met in .

order to meet ' the assumptions "..f *arJhat ema_-af i cpat a-1 sidsnts.

Qe'pba in tb CoAEOPERAmaq Lmits IEt. Marg '

The power imbalance anve d f t:d L- Tig.... ;.:-1. 4 2_. - fand the insertion limit curves m :: 2.1-j - > 2.1-3Jare based on LOCA analyses which have defined the maxsmum

~

ear heat race such that.the maximum clad atemperature LOCA. vill not exceed ' the Final Acceptance Criteria of 2200'T following Operation outside of the power imbalance envelops alone does not con-

~

stituta a situation that would cause the Final Acceptance Critaria to be ex-caeded. should a LOCA occur. The power imbalancia anvelope represents the bound-ary of operation limited by the Final Acceptane Critaria only if the . control rods are at the insertion limits, as define b _ ir;; ~2.1 2 M ? _ li3)and if l the steady-stata limit QUADRANT POWER TIL t introduced by applicatiert of: ona conserva ism is

, & bgopedigMgpetr

a. Nuclear uncertainty factors. w__ -

b. Thermal calibration uncertainty.

c. Tual densification effects.

d. ' Hot rod z. manufacturing tolerance factors. -

e. Potential fuel r'od bow effects. -

The ACTION statements which parait 11mitad variations from the basic require-mants are accompanied by additional restrictions which ensures that the orig-inal criteria are met.

The ' definitions of the design limit nuclear power peaking factors as used in these specifications are as follows: -

T N Nuclear heat flux het channel factor, is defined as the maximum local fuel rod linear power density divided by the average fuel rod linear power den-sity, assuming nominal fuel pallet and rod dimensions.

jDAVIS-BESSE, UNIT 1 3 3/4 2-1 Amendnent No. .R,Jr,45

- _ _ _ - - - _ _ . - - - _ - 4

1 Docket Number 50-346 J

,Lic:n;3 Number NPF-3 '

AD0ll10 hat CHANCES PRiv1005LY m j S;ric1 Number 1691 Attachment 2 PROPOSED 61 ttliER Page 25 gg g g 52.9 g f/5/69 ADMINISTRATIVE CONTROLS i

l l

microcuries per gram as a function of time for the duration of-the specific activity above the steady-state level; and (5) The ,

time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reporta of operating statistics, shutdown experience and challenges to the Pressurizer Pcwer Operated Relief Valve (PORV) and the Pressurizer Code Safety Valves shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington. D.C. 20555, with a copy to the Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.

m &m rre COREOPERATING LtMIT3 REPORT 3 c,.9.i.7. I wa,t A) h DAVIS-BESSE, UNIT 1 6-16

_ _ _ _ _ _ - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - ~ _ _ _ _ Amendment No. 8.

_ su.vt -- - _ - -

y .

' ". , Dock 2t Number

.Licznst Nurb2r 50-346 NPF-3 Serial.Numbar 1691

> Attachment 2 1hSEd 1M Page 26' CORE OPERATING LIMITS REPORT y

6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING. LIMITS REPORT.before_each reload cycle and any remaining part of a-reload cycle for the-following:

3.1.3.6. Regulating Rod Insertion Limits 3.1.3.7 ~ Rod ~ Program 3.1.3.8 Xenon Reactivity 3.1.3.9 Axial Power Shaping Rod Insertion Limits

.3.2.1 AXIAL-POWER IMBALANCE 3.2.4- QUADRANT POWER TILT The analytical methods used to determine the core operating limits addressed by~the individual Technical Specifications shall be those previously reviewed and. approved by the NRC, specifically:

1) BAV-10122A Rev. 1, " Normal Operating Controls", May 1984

2) .BAV-10116A, " Assembly Calculations and Fitted Nuclear Data", May 1977-

3) BAV-10117P- A, " Babcock & Wilcox Version of PD0 User's Manual", January 1977

4) BAV-10118A, " Core Calculational Techniques and Procedures", December 1979.

5)':BAV-10124A, " FLAME 3 - A Three-Dimensional No'dal Code for Calculating Core Reactivity and Power Distributions". August 1976

6) BAV-10125A, " Verification.of Three-Dimensional FLAME Code", August 1976

7) BAV-10152A, "N0ODLE - A Multi-Dimensional Two-Group Reactor Simulator", June 1985

8) BAV-10119, " Power Peaking Nuclear Reliability Factors", June 1977 The methodology for Rod Program received NRC approval in the Safety Evaluation Report dated .

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revision or supplements thereto, shall be provided upon issuance for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

- - - - - - _ _____ _ - _ _ __ _ D

3 ~

DocketINumber 50-346'-

4 :. '-.

.l Lic;n:2 Number ' NPF i 1 Serial Number 1691-

Attachment 3

Page'l

( w SAMPLE TOLEDO EDISON COMPANY DAVIS-BESSE UNIT 1.

CYCLE 6' CORE OPERATING LIMITS REPORT-v REVISION O l.

l'

~

l p

r :

1, a'i . _ . - _ _ - . - _ - - ------_--_--_----_____A

l .

, Dock;t Nu ber 50-346 Lic n:a Number NPF-3 4 f, Serial Number 1691 l Attachment 3 Page 2 TOLEDO EDISON DAVIS-BESSE UNIT 1 l CYCLE 6 CORE OPERATING LIMITS REPORT REVISION O 1.0 Core Operating Limits This Core Operating Limits Report for DB-1 Cycle 6 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 the references.

The following cycle-specific core operating limits are included in this report:

1) Regulating rod insertion limits

2) Rod program group positions

3) Axial power shaping rod insertion limits

4) Axial power imbalance operating limits and

5) Quadrant power tilt limits.

2.0 References

1) B&W Fuel Company, Topical Report BAV-10122A Rev. 1, " Normal Operating Controls", May 1984

2) B&W Fuel Company, Topical Report BAV-10116A, " Assembly Calculations and Fitted Nuclear Data", May 1977

3) B&V Fuel Company, Topical Report BAV-10117P-A, " Babcock & Wilcox Version of PD0 User's Manual", January 1977

4) B&V Fuel Company, Topical Report BAV-10118A, " Core Calculational Techniques and Procedures", December 1979.

5) B&W Fuel Company, Topical Report BAV-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions", August 1976

6) B&W Fuel Company, Topical Report BAV-10125A, " Verification of Three-Dimensional FLAME Code", August 1976

7) B&W Fuel Company, Topical Report BAV-10152A, " NOODLE - A Multi-Dimensional Two-Group Reactor Simulater", June 1985

e, ~ ,

. a .

. .. -;, ,. 1 f b-;m h' .__ _ . , .

, .),1

,. ;g " 3m Docket Nu:.ber 50-346' ,

> ' ,+ , .g . -

.p Lic.nca Numb:r NPF-3

. '. y' ,

NM ' '

. Serial Number 1691' E- Attachment 3' ' '

Page.3. ,

8) : B&W Fuel Company, Topical Report BAV-10119,:" Power' Peaking Nuclear.

Reliability Factors",! June'1977. - 3 --

.9) Letters.from- to- ,. dated , . 1989.' (NRC. "

SER for Rod Program) ,

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.Docitt Number 50-346 SAMPLE

. Lic:nse Nuntber NPF-3 Serial Number 1591 Attachment 3 Page 4 h Q ' ( "l Ep n . I Figure 1 Regulating Group Position Limits,_

0 to 3251 10 EFFD, Four RC Pumps --

Davis-Besse 1, Cycle 6 This Figure is referred 5,

to by Technical Specification 3.1.3.6 (300,102)

(258,102) ,. ,,

100 - Power Level (270,'102)

Cutoff = 1007,

'(270,92) _

SHUTDOWN E MARGIN g 80 -

LIMIT (250,80) c.

N z

$ UNACCEPTABLE G OPERATION OPERATION 60 -

8 RESTRICTED E (170,50) m (180,50) o 40 -

5 n.

! (128,28.5)

E

? 20 -

ACCEPTABLE OPERATION 4 (0.0,5.0) 0 ' ' '

O 100 200 300 Rod Index (*, Withdrawn)

GR 5 i '

0 75 100 GR 6 i ' ' '

O 25 75 100 GR 7 ' ' '

O 25 100 Note 1: A Rod Group overlap of 25 25% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

1 l

, < i i' Docket Number 50-346 . SAMPLE

.

Lic;nno Number NPF-3 Serial fiumber 1691 I Attachment 3 i Page 5 j

Figure 2 Regulating Group Position Limits After-325+ 10 EFPD, Four RC pumps, APSRs WitEdrawn -- Davis-Besse 1, Cycle 6 This Figure is referred to by Technical Specification i 3.1.3.6 (266.102) (300,102) 100 -

Power Level '(270,102)

Cutoff = 100%

SHUTDOWN-(270,92)

_ MARGIN f

n.

80 - LIMIT (250,80) a f

=

OPERATION 5 60 -

UNACCEPTABLE

$ OPERATICN

= (176,50)

(180,50) o f 40 -

E f

2 (136,28.5)

E e 20 -

ACCEPTABLE OPERATION i (0.0,5.0) 0 100 200 300 Rod Index (% Withdrawn)

GR 5 ' ' '

l 0 75 100 l

l GR 6 ' ' ' '

O 25 75 100 GR 7 ' ' '

0 25 100 Note 1: A Rod Group overlap of 25 25% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

l ..

i

S'

~' ' Dock 3t Number 50-346 SAMPLE Lic:nsa Nu2ber NPF Serial Number 1691 *

' Attachment 3 Page 6 Figure 3 Regulating Group Position Limits, O to 3251 10 EIPD, Three RC Pumps --

Davis-Besse 1, Cycle 6 This Figure is referred to by Technical Specification 3.1.3.6 100 -

S 80 - (258,77) (300.77) 3 7 -G

( 0,77)

I SHUTDOWN 1 MARGIN *(270,69.5)

$ LIMIT.

- 60 -

b, (250,60.5)

S

E a:

w UNACCEPTABLE OPERATION OPERATION .

L RESTRICTED 1! 40 -

(170.38)

$ (180,38)

.E 5

O (128,21.8) ACCEPTABLE OPERATION 0 ' i i 0 100 200 300 Rod Index (% Withdrawn)

GR 5 ' ' '

3 75 100 GR 6 i- ' ' '

0 25 75 100 GR 7 ' ' '

O 25 100 Note 1: A Rod Group overlap of 25 15% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

4

._.m _ _ ._ __ .____._.m._. _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 Dock 3t Nu;ber 50-346 SAMPLE License Number NPF-3 Serial Number 1691 Attachment 3 Page 7 Figure 4 Regulating Group Position Limits After 325 10 EFPD, Three RC Pumps, APSRs Withdrawn -- Davis-Besse 1, Cycle 6 This Figure is referred to by Technical Specification 3.1.3.6 100 -

E 80 -

(266,77) (300,77)

$ SHUTDOWN -E O

"- (270,77)

MARGIN y UNACCEPTABLE LIMIT (270'69.5) cc OPERATION E

~ 60 -

250,60.5) e W

[ OPERATION (176,38) RESTRICTED

$ 40 .

$ (180,38) b 5

g 20 -

(136,21.8) c.

ACCEPTABLE O ' ' '

O 100 200 300 Rod Index (% Withdrawn)

GR 5 ' ' '

O 75 100 4

GR 6 ' ' ' '

0 25 75 100 GR 7 ' ' '

O 25 100 Note 1: A Rod Group overlap of 25 15% between sequential withdrawn groups 5 and 6, and 6 and 7 shall be maintained.

l

~

, t Dockat Nuzber 50-346

'Licin3a Nuzber NPF-3 SAMPLE. nD Ep 5%

E7J 3

. Serial Number 1691 Attachment 3 Figure 5 Control Rod Core Locations Page 8 and Group Assignments --

Davis-Besse 1, Cycle 6 y This Figure is referred f N to by Technical.So*eification 3

3.1.3.7 A

3 4 6 4 C 2 5 5 2 D 7 8- 7 .8 7

'E 2 5 5 2' F' 4 8 6 3 6 8 4 G S 1 1 5 H W- 6 7 3 4 3 7 6 -Y K 5 1 1 5 L 4 8 6 3 6 8 4 M , 2 5 5 2 N l 7 8 7 8 7 0 l l 2 5 5 2 P l l l 4 6 4 R ,

Z 1 2 3 4 5 6 7 8 9- 10 11 12 13 14 15 Grouo No. of Rods Function 1 4 Safety 2 8 Safety 3 4 Safety X Group Number 4 9 Safety 5 12 Control 6 8 Control 7 8 Control 8 8 APSRs Total 61

SAMPLE 4 r Docket Nurb2r 50-346 License. Number NPF-3 T Serial Number 1691 Attachment.3 l

Page 9 Figure 6 APSR Position Limits, O to 3251 10 EFPD,.

Four RC Pumps -- Davis-Besse 1, Cycle 6 This Figure is referred to by Technical Specification - 3.1.3.9 RESTRICTED REGION

=

100 - (0,102) (100,102) '

SO -

E a.

a

!! 60 -

!! PERMISSIBLE es OPERATING REGION W

E u

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a E

L' E

5 g 20 -

s 0 , , , , , , , , , ,

0 10 20 30 40 50 60 70 80 90 100 APSR Position (% Withdrawn) i 1

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SAMPLE

~ Docket Number 50-346 -

License Number NPF-3 Serial Number 1691 h $ ,b ,g E# nI I Attachment 3 Page 10

, Figure 7 APSR Position Limits After 3251 10 EFPD, Three or Four RC Pumps, APSRs Withdrawn --

Davis-Besse 1, Cycle 6 This Figure is referred to by Technical Specification 3.1.3.9 100 .. . ..

E 80 -

m.

a B

W 60 ,, APSR INSERTION NOT ALLOWE0 3: IN THIS TIME INTERVAL l

' 8 2

x D 40 -

e b

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! 20 -

E 2

O ' ' ' ' ' ' ' ' '

O 10 20 30 40 50 60 70 80 90 100 l

APSR Position (% Withdrawn) l l

SAMPLE 8

Dockat Nuiber 50-346

'+.- Lic;nra Number NPF-3 Serial Number 1691 Attachment 3 Page 11 Figure 8 APSR Position Limits, O to 3251 10 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 6-This FiFure is referred to by Technical Specification 3.1.3.9 100 -

80 -

RFSTRICTED y REGION f

c.

(0,77) (100,77 J

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y 40 - PERMISSIBLE g OPERATING REGION t

h b

8 n- -

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l 0 ' ' ' *

e t i e i 0 10 20 30 40 50 60 70 80 90 100 APSR Position (% Withdrawn) i

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?-

~ *,

! Docket Number 50-346 SAMPG

1Lic:nna Number:NPF-3 .,,,

Serial Number 1691 g

1. Attachment 3 e Page 12 Figure 9 AXIAL POWER IMBALANCE Limits, Four RC Pumps -- Davis-Besse 1, Cycle 6 1 This Figure is referred to by Technical Specification 3.2.1

- 110

(-20,102). (15,102)

" 100

(-25,92) a (15,92)

- 90 ,

2

(-28,80)< y--20 ,(20,80) a.

- -70 w

iE . .60 S

(-28,50) o j . 30 o (20,50)

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- 40 RESTRICTED PERMISSIBLE E - - 30 REGION OPERATING $

REGION 5- - ~ 20 E

- - 10 t ' ' ' ' ' ' '

'i

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE (*)

p i

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7- #' Docket Nu;ber 50-346- SAMPLE

1 Licenga Nurber NPF-3 tus ==

Serial Number 1691

' Attachment 3 {

Page 13 Figure 10 AXIAL POWER IMBALANCE Limits, Three RC Pumps -- Davis-Besse 1, I Cycle 6 l This Figure is referred to by Technical Specification .

3.2.1 -

. 110 j 100 90

~~

(-15,77); , ,

(11.25,77)

(-18.75,69.5) . 70 t (11.25,69.5) 2

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