Text

Proposed Tech Specs,Including Page 1-6c,re Relocating cycle-specific Core Operating Limits
	ML20245C235
Person / Time
Site:	Davis Besse
Issue date:	06/16/1989
From:	; TOLEDO EDISON CO.
To:	;
Shared Package
ML20245C209	List: ML20245C208; ML20245C230; ML20245C235;
References
	NUDOCS 8906260101
	Download: ML20245C235 (42)
	v • d • e

- - - - - - - _

' ' Docir$tNumbar50-346 License Dumber NPF-3

' Serial Number 1668 Attachment 1 Page 4 AfDEX ll DEFINIff0NS SECTION PAGE 1.0 DEFINITI0MS (Continued)

SOLI DI FI CATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6a OFFSITE DOSE CALCULATION MANUAL (0DCM)................ 1-6a GASEOUS RADWASTE TREATMENT S YSTEM. . . . . . . . . . . . . . . . . . . . . 1-6a VENTI LATI ON EXHAUST. TREATMENT S YSTEM. . . . . . . . . . . . . . . . . . 1-Ga 3 PURGE-TURGING......................................... 1-66 VENTING............................................... 1-6b MEMB ER (S ) 0 F THE PUB LI C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6b S_ITEB00HDARY......................................... 1-6b UNRESTRICTED AREA..................................... 1-6b rD EWAT E R I N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l.-6b OPERATIONAL MODES (TABLE 1.1)......................... 1-7 FREQUENCY NOTATION (TABLE 1. 2) . . . . . . . . . . . . . . . . . . . . . . . . 1-6

~m CaecmAm bam E" " %c vv . t ,.. vd) i l

1 1

DAVIS-BESSE. UNIT 1 Ia Amendment No. E5 1

I hP J

f

l

. Dock,et Number'501346 Lit:n;2 Number NPF-3 L 52 rial Number 1668

' Attachment 1 P ge:5 DEFINITIONS e we .- - - , .

_y _

CORE OPE RATtMG b(MtTslEPoRT l,4 l %c Core OpeRArix: l.iuiTrTemer is EL, ami1- sp,c,-(c documeal. Ad. provides cove operating li mits fpr the curreal reload cycle.%ese cycle spcifik core geraby li mits shaR be determiaca for eact, reload eqcle in accordace' win f 3 pectpcation 6.9.1.1.7tamt c>per % wimm Rese core op,eatig l imits is. addressed in individual s7ecifcabs.

v--

i DAVIS-BESSE, UNIT 1

, c p-' Dock'et Nuxber 50-346

& Liccnra Nurber NPF-3 S rial Number 1668 Attachment 1 P:ge-6 REACTIVITY C0!: TROL SYSTEw.S MODERATOR TEMPERATURE COETTICIEh7 LIMITING CONDITION FOR OPERATION m, - . .-

3.1.1.3 dhg madsrutter e- 7 -entrea p - M4r4-ne_ N gi e b1ainhNed w h dw w. etape G its prov.aca Us e CoRECPERATtW, L18iTs EPORT'.

3.'fi.ess posa lve tnan 0.y = 10-" tk/k/*F whenever THER.4AL P0kTR is < 95%1f'

( RAAr b m.tQd.AL POWER, /

( i f.4 Less positive than~0.0'?-1

"^s F 7 henever THERMAL POWER is 2 95% of '

, } RATED THERMAL P0kTRdiuf ht

[ t c- regia 1 to or less negative than -3.0 x 10~" .tk/k/* nam TEEFEAL _POWERp APPLICABILITY: MODES 1 and 2*#.

ACTION:

With the moderator temperature coefficient outside the above limits, be in at least HOT STANDBY vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMEh75 4.1.1.3.1 The MTC shall be detettined to be withiniftsilli3ts by confirmatory l measurements. MTC measured values shall be extrapolated and/or compensated to per=1t direct comparison with the above li=its. "

4.1.1.3.2 The MTC shall be determined at the following frequencies and I THERV.AL P0kTR conditions during each fuel cycle: -

a. Prior to initial operation above 5* of RATED THERMAL P0kTR, af ter each fuel loading.

1

b. At any TEEEMAL PokTR, within 7 days af ter reaching a RATED THEL".AL P0kTR equilibri'.:= boren concentration of 300 ppm.

I.

l I

With k,ff 2 1.0.

See Special Test Exception 3.10.2.

DAVIS-BESSE,'JIT 1 3/4 1-4 Amendment No. 45

n c

1 DocNe'tNumber50-346- I

'Lic:n n Nh;ber NPF-3 '

'S: rial Number 1668 I ADDlil0NAL CHANGES PREVIOUSLY p ", f *" PROPOSED By LETTER Serial No. I@7 Date H/2 /87 REACTIVITY CONTROL SYSTEMS ACTION: (Continued) i c) A powerd' distribution mgp is obtained from the-incore detectors and F and F0 are i{

their 1imits wiShin 72 $ours. 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 i reduced to < 70% of the THERMAL 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 k,5 YY*h9 M E I5 T 5 Or. U _. N t5e'YHYR kl.-NUiNk i s.na e res r1cted pursuant to Specification 3.1.3.6 during subsequent operation.

&( b redy witW acceptable opudi g posifiono limils SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each control rod shall be determined 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 i be OPERABLE by movement of at least 2% in any one direction at least i once every 31 days. l l

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

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

' Dockst Nu:ber 50-346 Lice.nsa Numb:r NPF-3 S rial Number 1668 Attachment 1 Paga 8 REACTIVITT C0!TTROL SYSTEMS REGULATING ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION rn 3M_hatingJojlgg0pps i .: n t i ait- a : 5.

i shall beflfeited in ph,.ic.1

= Figures-3rl-C.ud -2L, 36 Se, .nd -3b. f.-ro]d greep en-- e' 5, eri

< -p 2of r-2515% sh='l be sinteined L6.--a .equential .-ithd avn )j g

ps; Ein e a wi thin h sucp.ble o e , a bi ,, O~i ts yw J rea u tat in, rod desikk. emvid ed 6 d e Co4E CPERATitJG L yr,s R op7 APPLIYABY1NT N 0f$5 ACTION E

Vith the regulating rod groups inserted beyond thesheAr4> l limits (in a region other than agcce table operation), or with any group surveillance sequencetesting or overlap to g iTi F,/

pursuantoutside limits, except for the g(Spgiticar4nn

_ . , either LI A12 l

s

a. auotable coe. ti ,9f Restore or the regulating groups M tile-dimits3 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , l b.

Reduce THERMAL POWER to less than or equal to that fraction of RATED

<THER!iAL t$c /: "fWvithin POVER2vhich is allowed hours, or by the rod group positioruMhe lia."

u ts c.

Be in at least HOT STANDBY vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE:

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

See Special Tes t Exception 3.10.1 and 3.10.2.

tVith k,gf 1 1.0.

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

, 7-

r; _, ci ,'

.'Dockht1Nuber)50-346-

}Lic:nsinumberNPF-3 i Serial-Number 1668 -

['

lAttachment 1 .l Page 9- 1 l

)

REACTIVITY CONTROL SYSTEMS REGULATING ROD INSERTION LIMITS

?

SURVEILLANCE REQUIREMENTS' Ac.ceph55 i 4.1. 3. 5 . T os iophh requiatin group shall'be determined to be within th --- Len,_1=Rn_ce add _ ccr,a; limits at least' once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months excep w hen:

a.. The regulating ro'd insertion limit alann 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 .

DAVIS-BESSE, UNIT 1 3/4 1. 27 a

Docket Nurber 50-346

'ILicen3'Nu ber NPF-3 l

S; rial Number 1668 :

3

? Attachment'l-Pcge 10

\

Figure 3.1-2a Regulating, Group Position Limits, /

0 to 325 10 EFPD, Four RC Pumps -- '

Davis-Besse 1, Cycle 6 ./ ;

D

'N.

100

\

- P6wer Level (258,102) __

(300,102) 3 (270,102)

Cut'off = 100%

\'N (270,92) i SHUTDOWN E

g 80 -

\' -

MARGIN LIMIT (250,80)

.s ,,

c-J N\ '

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w' UNACCEPTABLE N

'A OPERATION OPERATION g 60 -

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- p RESTRICTED

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C 70,50%' '

o (180.50) ea .

5 40 -

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g \ l' g

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/ (128,283) b /

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$ 20 - '

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, . ACCEPTABLE

/ '0PERATION 4 (0.0,5.0)/ \

0 ' ' ' '

0 / 100 200

\ 300

' Rod Index (% Withdrawn) \

GR 5 i i i 0 75 iu:) N,

' 1 GR 6 i '

i i '

1 0 25 75 100 !

GR 7 i ' '

0 25 10 1

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i N

\ -i DAVIS-BESSE, UNIT 1 3/4 1-28 Amendment No. 11, 33, 45, ' :

61, 80, 123

EE ,

i. 1 x., .. 1

'; .... Dock 3t Number 50-346

)'Lic';nsa Nu;ber NPF-3

~

i

- 5: rial Number 1668 ;

Attachment 1 )

P ge 11 ,

Figure 3.1-2b Regulating Group Postion Limits After N. . 325 10 EFPD, Four RC pumps, APSRs Withdrawa - Davis-Besse 1, Cycle 6 j

'y wM

\

(266,102 (300,102)-

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-l 100 'q Power Level , (270,102) !

xCutoff = 100%

( 0,92) !

SHUTDOWN

\ MARGIN 80 -

\\ LIMIT % (250,80)

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=

s OPERATION

- 60 -

\ RESTRICTED UNACCEPTABLE -

s OPERATION 1 (17 .50) (180,50) e !

p j 40 -

E f \

. (136';28.5)

E \

f 20 -

/

ACCEPTABLE

\ OPERATION i (0.0,5.0, 0

's J 0

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/ 100 Rod Index (*.' Withdrawn) 200 'N N

300 GR 5 '

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0/ 75 100 \

/ GR 68 ' ' '

0 25 75 100 '

GR 7 ' ' '

y 0 25 x100 f s

/ 'N {

,/ x <

/ 's \

1

/ DAVIS-BESSE UNIT 1 3/4 1-28a Amendment No. 11, 33, 42 \

45, 61, 80, 123 4

r

'c Number 50-346 Do'ket bicench Number NPF-3 Serial Number 1668 Attachment 1 Page 12 /

} \ Figure 3.1-3a Regulating Group Position Limits, jr

\ /

0 to 325 10 EFPD, Three RC Pumps -- '

Davis-Besse 1, Cycle 6

.x _- -

/

/'

y 1

100

/

\ !

\ \

l 80 - 258,77) 00,77) 2

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SHUTDOWN [ '

(270,69.5)

MARGIN 5

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\ (250,60.5) I

$ \

y 40 -

E T N h l170,' )

. ET TED 8 (180,38) l b '

a.

i 50 2 4 -

/ (128,21.8) ACCEPTABLE

\ OPERATION s

0 ' ' '

0 / 100 200 300 Rod Index (% Withdrawn)

GR 5 ' / ' ' '

0

/ 75 100

.' GR 6 i ' ' ' \

25

/ 0 75 GR 7 '

0 100 25 s

100

/ \

l

/ DAVIS-BES5?. UNIT 1 3/4 1-29 Amendment No. 11, 33, 41,\

j' 45, 61, 80, 123 \

/ _

)

.- Docket Nurber 50-346 i--:b'

' ^

, ':Lic:nsa

- Nuzber NPF-3 Serial. Number 1668.

i : Attachment 1 Page 13 '

N Figure 3.1-30 Regulating Group Position Limits N '

After 325 10 ETPD, Three RC Pumps, APSRs Withdrawn -- Davis-Besse 1, Cyc d _

pr N.\ 3ELETGb

/

\ /

\

- 100 -i / .l

/ :

.I s i t

's /

!- 2 80 -

s (300,77)

'p266,77) 5HUTDOWN M 3 I E x MARGIN / (270,77) l g UNACCEPTABLE LIMIT / (270,69.5) cc OPERATION E 60 -

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', / 250,60.5) l

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/

{ y OPERATION a 40 - '(j .38) RESTRICTED 5 '

(180,38)

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$ /

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(136,21.8) e

,' s ACCEPTABl.E

/ GPERATION

'(0,4.25 ) / , ,

0 / 100 200 N 300 )

/ Rod Index (% Withdrawn) i GR 5 ' ' ' '

0 75 100 GR 6 ' ' ' '

0 to to 100 GR 7 ' ' '

0 25 100 l

- I

/

/ g l

DAVIS-BESSE, UNIT 1 3/4 1-29a Amendment No. 11, 33, J.2, \

45, 61, 80,123 \

j ,

' ~' '

bockat Nurbar 50-346

+ : .L ic nsa Number NPF-3 4

Serial Number 1668 Attachment 1 Page 14?

L REACTIVITY CONTROL' SYSTEMS

l. R00 PROGRAM-LIMITING CONDITION FOR OPERATION e-_=

3.1.3.7 Each control-re NQ 'M

?, safety S M and APSR)'shall be pro--

gammedt o erate in t ore _ .

_ land rod group specified in s.,.-4.

'%.iiere CeRECPERATme. Lmirs TEPoRT . '

w J APPLICABILITY: MODES 1* and 2*.

ACTION:

With any control rod not programmed to operate as specified above, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEILLANCE REQUIREMENTS 4.1.'3.7

a. Each control rod shall .be demonstrated to be programed to operate in the specified core position and rod group by:

1. Selection and-actuation from the control room and verifi-cation of rmvement of the proper rod as indicated by both the absolute and relative position indicators:

a) For.all control rods, after the control rod drive patches are locked -subsequent to test, reprogramming or maintenance within the panels.

b) For specifically affected individual rods, following maintenance, test, reconnection or modification 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. 3 j

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

See special Iest Exceptions 3.10.1 and 3.10.2.

DAVIS-BESSE, UNIT 1 3/4 1-30 Amendment No.11 )

1

' Dock $tNurbar50-346

Lictn:2 Nurber NPF-3 S: rial Number 1668 Figure 3.1-4 Cait.o1 Rod Core Locations

' Attachment 1 and Group Assignments --

-Pege-15 Davj s-Besse 1, Cycle 6 y

A

.N A \

g 4 6 4

'N C \ 2 5 5 l2 /

D \ 7 8 7 8 7 /

\

E 2 S 5 f F 4 \ 8 6 3 6 8/ 4 G S \. 1 1 / i, H W- ,6 7- x 3 4 3 / 7 6 -Y K 5 1 1

/ 5 L 4 8 6x 3 / 6 8 4 M , 2- 5 \ / 5 2 N l 7 8 ( 8 7 o l 2 3 '

s 5 2 P l l l ,F 6 \ 4 R i i/ \

N Z \ .

1 2 3 4 5 6 7 8 9 10 11 k 13 14 15 Group No. of Rods Fun \

ction 1 . 4 Safet'ys 2 8 Safety .

3 4 Safety \

X Group Number 4 9 Safety !

5 12 Control 6 8 Control 7 8 Control 8 8 APSRs N Total 61

\

s DAVIS-BESSE. UNIT 1 3/4 1-31 Amendment r:o. 11, 33, 45, \

61, 80, 123 \

5 4 JDsckst.Nunber 50-346i

License Number NPF-3

> Serial Number 1668~

' Attachment 1 3

' Page 16 REACTIVITY CONTROL SYSTEMS XENON REACTIVITY LIMITING CONDITION FOR OPERATION 3.1.3.8 THER%L 29WER shali.not be increased 'above the power level cutoff -

specified'i ? .g,ur: f C Q h u f +he ellowing y l satisfied:. th'**uetAue am~u3 IW as Yo - re%ueiy ro psiha'_p' ici.J l in %, CORE C)?Efi ATsuG L a H irs R EPoRT*, J _

^

a. Xenon. reactivity is within 103Mthe equilibrium l 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 l THERMAL POWER for a period exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in the-soluble poison control mode, excluding xenon free start-ups. l I

APPLICABILITY: MODE 1.

ACTION:-

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

SURVEILLANCE REQUIREMENTS 4.1. 3. 8 Xenon reactivity shall be detennined to be within 10% of.the equilibrium value for RATED THEPMAL POWER and to be approaching stability or it shall be determined 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 ciitoff.

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

.' Dock,et Nusber 50-346

'Lic nsa Nu-ber NPF-3

5:4i01 Nu ber 1668

.)

Attachment 1 I Page 17 REACTIVITT CONTROL' SYSTEMS AXIAL POVER SHAPING ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION

-w 3.1.3.9 The axial power shaping rod group shall Mmi!M in phy ieel E'-h n. Piswes 11-56 -5t, an. - .c.

Win % < h' Pra bic opeah g its for ** r pe d Et,2 N U. , Cc R E CPE R Af g hic llM i rs RE Pe.m i .

APPO M ITY,: 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 POWER to less than or equal to that fraction of RATED THERMAL POVER vhich is allowed by the rod group position using the above figures within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

c. Be in at least HOT STANDBY vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l

\

1 SURVEILLANCE REQUIREMENTS 4.1.3.9 The position of the%[jEp'tible x1Mr shaping o rod group shall be determined to be within thel ola limits at least once every 12 l hours except when the axial,/jg?a' pover s ping rod insertion limit alarm is inoperable, then verify the group to be vithin th 1:i:~rilN g at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . l Acce p t Al e o pe ra ti .,.

,"Wowbui)

Vith K,gf 1 1.0.

DAVIS-BESSE. LUIT 1 3/4 1-34 Amendment No. 33.

42, 45, 61, 69.

80,123

-D ekst Nu ber.,50-346 1*ic:ns5NurbarNPF-3 '

Serial Number 1668 ;

Attachment ~1 !

Page 18 Figure 3.1-Sa APSR Position Limits,.0 to 3251.10 EFPD, s

Four FCJumpg- Davis-Besse 1, Cycle 6 p

\ f 3ELETE S '

/

RESTRICTED REGION

?

100 P 0,102) (100,102) 'z

s. .

N \

N 80 -

\

s

. a.

N N !

a b

60 -

j P RMISSIBLE a OPERATING REGION l d

I o 40 -

$ \

Ns ;

g /

(

i / \ '

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20 -

/

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/ \

O' ' ' ' ' ' ' ' ' ' '

j 0 10 20 30 40 50 50 70 30s 90 100

\

APSR Positi0n (?. Withcrawn) Ns T\

N l i DAVIS-BESSE, UNIT 1 3/4 1-35 Amendment No. 33, 45, 61,

/ 30,123

_ _ _ _ - . _ _ _ - - . . . _ _ d

.r I'- 'Do'ckst Nu;ber 50-346 -

'- ' " - !Lic;nfa Nu ber NPF-3 L. Serial Number 1660

.-Attachment 1

'Page 19

\ Figure 3.1-Sb APSR Position Limits After

.\ . 3251 10 EFPD, Three 'or four RC ,e

\ Pumps, APSRs Withdrawn --

\ Davis-Besse'1_, Cycle 6

\

\\

\

100

'N /

E - 80 _ x 5 N 2

N W 60 - APSR INSERTIONA 0T ALLOWED A- IN THIS T INTERVAL S

E CE - /

% 40 -

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, \

e N

/ N

[

i 20 - -

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2

/

0 ' ' ' ' ' ' i ' '

20 30 40 50 60 '90 0 / 10 70 50 100

,/ APSR Position (". Withdrawn)

\

/ \,

/ s

y j

\ l l

Ns ;

, s

/

/ DAVIS-BESSE, UNIT 1 3/4 1-36 Amendment No. 33, 42, 45 s i 61, 80.123

\ ;

7, -_.

l k',:DocloetNurber50-346

' 1. Lic:n;p Nu;Mr NPF-3 S: rial Number 1668 )

Attachment l'

'P2ge 20

\. . Figure 3.1-5c .. APSR Position Limits, O to 325t 10 EFPD,.

\.

Three RC Pumps -- Davis-Besse 1, Cycle 6

/

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J.MLE i-,f /

L e-7

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2 : '

W (0,77) \ / (100,77) 1

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5 60 -

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S w /

5 /

t 40 - ,'

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PERMIS$1BLE 5 OPERATING REGION E \

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, s 1

$ / 'N e 20 -

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\ i i i , , i \ ' i 9 i i i fl 0 10 20 30 40 50 60 70 30 :00

)30 APSR Position (* Withdrawn) 1 i

' \ I

\ J N

\

l

,. DAVIS-BESSE, UNIT 1 3/4 1-37 Amendment No. 33, 45, 61 ;

/ 69. 80,123 j 'N j I

\ .. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ .

Dociat Nuxbtr 50-346 Licenza Nuzbar NPF-3 S: rial Number 1668 Attachment 1 '

Page 21 3/4.2 POVER DISTRIBUTION LIMITS AXIAL POVER IMBALANCE LIMITING CONDITION FOR OPERATION 3 a Q XIAL J )RE JRBALANEshall_be maintained _Vithin_theJ,4mi4s-shown 1 1 fon F4 guns 3.2-1 and 3.2 2. acc Pt*

Axi rvv.ded in the ORE CPERATsWq LlhiTS 'RE FORT.A' ec WG R In BAL AVc k opentiny Lits /

g-APPLI'C311 TIIM'0YiE'l above 40% TED THERMAL POVER.*

ACTION Vith AXIAL POVEE IMBALANCE exceeding the limits specified above, either:

a. Restore the AXIAL POWER IMBALANCE to withi,nd Q {mits_vithin 15 minutes, or a cc'<>ta uc o p mem.

v _.

b. Vithin one hour reduce power until# mbalance limits are met or to '

40% of RATED THERMAL POWER or lessi c g, ,

SURVEILLANCE REQUIREMENTS g y-.-

La ccep ta tJ< ownw.

4.2.1. The AIIAL POVER IMBALANCE shall be determined to be withirtv , '

limits at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 40% of RATED THERMAL" POVER except when the AXIAL POVER IMBALANCE alarm is inoperable, then calculate the AXIAL POWER IMBALANCE at least once per hour.

See Special Test Exception 3.10.1.

DAVIS-BESSE, UNIT 1 3/4 2-1 Amendment No. 33, 42, 45, 61, 69, 80,123

!Dockst.Nd:bbr 50-346

..- .,Lic;nco Numb:r NPF-3 -

Serial Number 1668

Attachment 1 l - Page 22 Figure 3.2-1

\' -

AXIAL POWER IMBALANCE Limits, Four RC Pumps -- Davis-Besse 1, Cycle 6

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i DAVIS-BESSE, UNIT I 3/4 2-2 Amendment No. 11, 33, 4 .

61, 80, 123

_ _ _ _ _ _ _ __ l

t

" .LDoc'k$t Nu;ber 50-346 Liesnca Nuzber NPF-3

' Y Serial Number 1668'

' Attachment 1 Page 23 Figure 3.2-2 AXIAL POWER IMBALANCE Limits,

'N.s Three RC Pumps -- Davis-Besse 1, ,e

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DAVIS-BESSE, UNIT 1 3/4 2-3 Amendment No. 11, 33, 45,

,. 61, 80, 123

Docket Nu;ber 50-346-

' Licdc2 Number NPF-3 ,

L S; rial Nu:ber 1668

[ .Attcchment 1 P:g3 24 1

POVER DISTRIBUTION LIMITS QUADPANT POVER TILT LIMITING CONDITION FOR OPERATION

/32d l!DLMADEANL20m 4 2-TsL16 3.2,-1. k e QCh TTLTahalLngl_.

Miw T t bGO' exceed 4t_Slaa_dy_

TLT f(c M/ed nr %State a/M_ oby/>riq ueq \

QtM1/ rA d%fcil" APPMI'TM,DE i W 1 above 15% of RATED THERMAL POWER

i ACTION:

a. Vith the QUADRANT POVER TILT determined to exceed the Stea.dy.~

Sta,Ie_Limij b,Lut. Jess _than or equal 3Je Transient _Limi_thf- $

debrie 4.2-1. m tu ce u: cf62Mr W6 '/d/h 57127/

/

1. Vithin 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s: l a) Either reduce the QUADRANT POWER TILT to within its Steady State Limit, or b) Reduce THERMAL POVER so as not to exceed TUERMAL POVER, including power level cutoff, allovat.le for the reactor coolant pump combination less at least 2%

for each 1% of QUADRANT 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-6 Flux-Flow Trip Setpoint at least 2% for each 1% of OUADRANT POVER ;

TILT in excess of the Steady State Limit.

2. Verifv that the QUADRANT POVER TILT is within its Steady Stat ~ Limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the Steady State Limit or reduce THERMAL POVER to less than 60% of THERMAL POVER allowable 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 THERHAL 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 POWER; subsequent POVER 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 erified acceptable at 95% or greater RATED THERMAL POVER.

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

I Dot)tetlNunher 50-346 4 J

"' ;Licensa, Number NPF-3 Serial Number 1668 A00iitoIML CHANGES PREVIOUSLV' s ! Attachment 1 -. PROPOSED SY LETTER Page 25' ,

SerialNo. I'/01 ' Date///2./av ,

POWER DISTRIBUTION LIMITS

' LIMITING CONDITION FOR OPERATION (Continued)'

b. . Vith the QUADRANT POVi.'R TILT determined ' to exe

~

he Transient Limit but less than. the Maximum Limit f ~1:h 2.L* , due to l misalignment.of either a safety, regulatin [~r'axaipower-.

shaping rod: 4 G72 cWMoN4 avWs daMr

1. Reduce THERMAL POVER at least 2% for each 1% of indicate QUADRANT POVER TILT in excess of the Steady State Limit

'vithin 30 minutes.

-t 2. Verify that'the OUADRANT POVER TILT is within its.

Transient Limit yithin;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 POWER to less than 60%

of THERMAL POWER 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 end ieouce the.High Flux Trip Setpoint to < 65.5% of THERMAL POWER allovable.

for the reactor coolant pump combination within the next 4 L' ' hours.

3. Identify and correct the cause of the out of limit condition-prior to increasing' THERMAL POVER; subsequent

-POWER OPERATION:above 60% of THERMAL POVER allovable for the reactor coolant pump combination may proceed provided that the QUADRANT POWER 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 acceptable at 95% or greater RATED THERMAL POVER.

c. Vith the OUADRANT POWER TILT determined to exceesi the Transient Limit.but less than the Max 2 mum Limitf- M 1 2 . M g due to causes other than the misalignment o a l

ing or axial power shaping: rods i Rgga_s,algtya,Iegulghg' ^^ 'd

1. Reduce THERMAL POWER to less than 60% of THERMAL POWER allovable 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 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 .

2. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POVER; subsequent b POVER OPERATION above 60% of THERMAL POWER 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

_ _ . _ _ _ _ l

J

'~ !

Doditat Nunber 50-346

. Lic:nra Nu2b2r-NPF-3 S; rial. Number 1668 e ' Attachment 1 Page 26

{'

P3VER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

d. Vith the OUADRANT POVE

\

Limit 4 M EiT 5 F ( Rreduce TILTTHERMAL determined POVERto to exceed the Maximum

< 15% of RATED 2_ hours. .

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47 bili)J i

SURVEILLANCE REQUIREMENTS i' 4.2.4 The QUADRART POVER TILT shall be determined to lbe ri din limits at least once every 7 days during operation above 1 % of'RITEDC THERMAL POWER except when the QUADRANT POVER TILT alarm is inoperable, then the QUADRANT POVER TILT shall be calculated atleast once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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.j DAVIS-BESSE. UNIT 1 3/4 2-11 Amendment No.123

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Attachment 4 J Page 11 Figure 9 AXIAL POWER IMBALANCE Limits, Four RC Pumps -- Davis-Besse 1, Cycle 6 i

This Figure is referred to by Technical Specification 3.2.1' '!

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