ML20005E753

Proposed Tech Specs Revising Sections 5.3 & 5.6.1.1 & Bases 3/4.9.3 Re Spent Fuel Pool Storage & Bases for Decay Time Prior to Fuel Movement

ML20005E753
Person / Time
Site:	Callaway
Issue date:	12/28/1989
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20005E752	List: ML20005E751 ML20005E753
References
ULNRC-2130, NUDOCS 9001100247
Download: ML20005E753 (4)

Text

L - . ' ' E , 7T

.__35+- j F, -3 1. -4 iJ. f

+

=]'

- M.

's rs%I(t21 fD .M,4,5 p k.;7 v<xy i A.. y' . .. c.j%'a.-.[.[i . g $ ,5 y.-[-tW;:;.

'N ' 3 - - -

.3.)

r i t t1

-a, st w .p,,

. 1

.,[_ '. hg ;c , *- * }

,. *d y

: ..L., ?

Y d- < -' # j !_

-%( .d i .

wnn" (ye , &s 's>t,Wk %% ' - ; ,,s z u" 4r %

> - 9, .rs

&s#

o n-W y Att2 hment 4,.e. g Y.. S. {%. ,

+ud - WM 4

M, ,- m '

io i

Mb4.xfg - W,h 1M n# .

w.

'ULNRC-2130 W 'g,n *

• ~ -

' h% f A L ':y 2,

I

[l

- -. #.:M33 i* y

,_hb.[,[fdl$ .ik.h '$ v'+

g .h :' ( j ., -

% , t* J, f N',t * #' "u;' m

.d . .

W 6

y;...;

i K wQa -

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

.,u,;

s am

. , ,' $,, s, _

n ,

x.

.z u.v..u. -- ts , yr ; . ., j O m + 1-y , g,

-};

3.' .% m.sinw.w t U.a.- qa.

n4 m

w'<

• gj; y ..;p. , s; a ;.g.5 t +

. > y_ > . pg <

' . , p;' .; ,

m 1y -

Ak 3 '

s ;

r

!,,, i

&y.,?j , " . ' i' 1 1 .

ytl > $ * +a* ,

g f, ty ., , ,

~

g a

,  ;. w ., , -

i 'mu ^

+ : 6

, (;

5

'y n 6' l,:?t ' d'2'_ , .

• ? r)'\ - 4 5 t ,

~.j 'M.p< f' ; '

• 4

(,,yg. n

, e v v

w r M, e '

>_ ;m'.

s ,

, .,7,-T.

/- 4 lj

s. . , 9 4';.,pg -

g 5 ..,4,;','T,N, "d } 'jI

,,  ! ~,), +

m. , .

<u,m.

. , ~ . :

an. n s.

1 < ~ -' f .m.. ' .- g; n A. "s. . ~

g  ;.v t t' *j.'.

,3 ',

' r' 6.:/ ,

p I M f ,. . +

~

..,', g ;'

F .h !

^

} .t

_ f 'l _l

.w s . 1 MARKED TECHNICAL < SPECIFICATION-PAGJE p > '

/ T:

$y ud,.a.;. ,o. .n.v . ,

4 i_,-. e ,

,,_.,Y- "

a_-  ! , ,,

m "'

r

-_A q N ':

, ' ~

Pagest: ! B 3'/.419-l a- - -

%aw;'g' .x;m. A pGg' - .y 3 p % .s .~ f US .D. ~' . .. Iib ' ' . -~ I ~ 'i' e

t a..

.ky i T. .. ,3,, . t ij. 5g ,'M[c ' ' ;'e s F

. n .

F g& . ' . . 4:

. -;f '

1.. i

?g^ '

m;; .p FX, .- @,s v. :. % , o a, , s s

so- _

r7.Q' p .

eyw *4:3e f yg pj w_ 3

' t ?' - , t ' s w]

.n :

%,W;wy:

?. . . > . , ,m t t

. .n. K W -

s

'i

• e,t' i

P.i ,

m.

m. . , m, o, u-8 ,

- . s

',i

' i:' .

f y . ,. + ,

e-vfe A.

'k_. .1, ! :

l-l- -- -

4 o ay,

%  % TT Q .)Q ,5m_ y h.  : ,

- .e.. ,

y n W? ?

e'f-* J V

8 ., -.~ r Q -+ . 'i. '

@M h 4

w -

ni : 2

+ -- ,

e 6 r

^ pen , , - .

2^.'.

~

l k '-- >

N' -

- ,y m,

[w _A w=w , ' '

t s . 8

,t n'u 1

. . ,1 g- a xi , . r cm"*

1. , ,i g

rt' g

s, e, e

-1

,I ,

e .. ;.n.+

~

c ;,ap

- . . ~.- ,

.j bpy r

4_

1 4 ,,-ic.,-.

.i r

i h,Y 2f T

3

^s ~ v -

y}

p!h -.>-<

, ~

L v.-

w..s p.

.,w

, c,f

,i J '4.e -

o..

g' 3 A S ( -} h 3

? , 9 i

.- ~ =,

, r

. t JA .'.:},'4ry' \ .yA i-t4

, ,s-1

<g

~

i.r m,, > ,

g . -

7 -% 4k c.

w a,.

%;.' y p.-

W (' g

_ 5-

,, f ,b_ \t -

A >

%' . r i

4 k; .1:

f' .#

('N t

~

a.i m, ,

i ~ ,-

i. -

• t i .n .

a  % ?w

,, y, >1 x ,- .

-g n ,

. ,s -

WW y=

s x ., ,i m.:Q n $

' h :1

"'l.._;,

.h is'kd * . ,

,?

f h;-h.f ,

• S(,.t*

, .h .h-

-b 3 ,.:5' r

, ~; - ,  ;

.~.'c I-4 b

,m,,

,~m, .

~

T h

, .n +

. p 3

xf.. ;y..

aj

?

IA -

• s, 1

-~ . .  ;

1 4'

, ..-. - mm .

l @,"

• 96o1100247;891228.-

1 .

t A

b ':L . Fu - F iPDReADOCK:05000483 a

PDC

~ a- - .

'. .S b,h .[ -y-p ^k9* (

~'

(

3' .]%

r,E '; j _-'

m ..

1 I 1

- Q , 5 > fh'f ,

~

. . , 5- t i h

{

ump.E naggM.~ .-.CM g, .

I +

-4=49 4 w r4 m . .w m,,,

A,,,.mJ-..,,,m.,,,,.g.,A.,,,,,.

, .;, ;,, ,;., y , , . _ . o

3/4.9 REFUELING OPERATIONS i

I BASES '

l 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. The limitation on K of no greater than 0.95. is sufficient to prevent reactor refueling operations. The locking closed of the required valves during criticality during,ff i i

refueling operations' precludes the possibility of uncontrolled boron dilution of the filled portions of'the Reactor Coolant System. -This action prevents flow to the RCS of unborated water by closing flow paths from sources of ,

unborated water.

These limitations are consistent with the initial conditions assu.ned for the boron dilution incident in the safety analyses.

• 3/4.9.2 INST.10 MEN 7ATION "

The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitorTng ca condition of the core. pability is available to detect changes in the reactivity 3/4.9.3 DECAY TIME The minimum requirement for rasetor subcriticality prior to movement of ~

irradiated fuel assemblies in the-reactnr vassal ensures that sufficient time has elapsed to allow the radioa'ctive decay of the short-lived fission products.

This k the.

d. Wgl

-t ndecay time is consistent a gctgaAtelo$ica with the'assumptien.s consepa, a,ut set kat poo used**A in 4

• 1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and -

OPERABILITY will-be restricted ensure that atorelease from leakage of radioactive material within containment the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

The OPERABILITY of this system ensures the containment purge penetrations will be automatically isolated upon detection of high radiation levels within containment. The OPERABILITY of this system is required to restrict the release of radioactive materials from the containment atmosphere to the environment.

The restriction on the setpoint for GT-RE-22 and GT-RE-33 is based on a fuel handling accident inside the Containment Building with resulting damage to one fuel rod and subsequent release of 0.1% of the noble gas gap activity, except for 0.3% of the Kr-85 gap activity. The setpoint concentration of SE-3 uCi/cc is equivalent to approximately 150 mR/hr submersion dose rate.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can.be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

CALLAWAY - UNIT 1 B 3/4 9-1 Amendment No. 20

a v DESIGN FEATURES

5. 3 REACTOR C0tf FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly nomally containing 264 fuel rods clad with Zircaloy-4, except that limited substitution of fuel rods by filler rods consisting of.Zircaloy-4 or stainless steel or by vacancies may be made if Justified by a cycle-specific reload analysis. Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maxion total weight of 1766 grams uranium. Reload fuel shall be similar in physical design to the initial corejoadirg and shall have a maximum enrichment of 4TM weight percent U-235. Fesu s,r* m ,- curs ccmn 94 us z. sa .,,. n n., o -u s - c.~n .~

3 ,c,r;'- daa9

.sNTRot R09 Asspeurs g;<;.~;j~ggy;c.+M.

,- . . ,, , n . ~. . . . m ~, v . 1

. E.3.2 Tha c.tre shall tentsin 33 full-length and.r-o . part-len3tir control rod i ess m611as. The fdil-length control rod assemblies shall contain a nmins1 142 '.nchet of ab3ceber anteriai. All control reds t, hall be Fafnit 4, silver-l.

~

indiumcadmium, or a mixture of both types. All centrol rods shall be chd l lt with stain'. ass steel tubing.

5_. 4 . QQOR CtF)LANf 5YSTEM D,ESIGN PRES $URE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of' the FSAR, with allowance for nomal degradation pursuant to the

applicable Surveillance Requirments, For a pressure of 2485 psig, and b.

I

c. For a temperature of 650*F except for the pressurizer which is

. 680*F.

T-y.2.25.

! 5.4.2 The total volume of the Reactor Coolant System, including pressurizer l and surge line, is 12,135 ,+ 100 cubic feet at a nominal Tavg of 557'F.

5. 5 METEOROLOGICAL TOWER t.0 CATION

5. 5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

CALLAWAY - UNIT 1 5-6 Amendment No. J2,23,24, 41.

c ug' f DESIGN FEATURES  :

)

5'.6 ' FUEL: STORAGE CRITICALITY .

The spent fuel storage racks are designed and shall be maintained 1 5.6.1.1 with'  ;

a. Ak eff equivalent to less than or equalm to 0.95 when flooded with p unborated water, which includes : :nn. .;M;; allowance f C -

higMr for uncertainties as described in Section 4ppof the FSAR.

w,g q

1. l h This is based on4mw uel with3 :r-f t:rt :f ' 5 iZt :r:: t Wk'y vj we J ( U-235 in Region 1 and n s;;ent fuel with combination of initial enrichment and discharge expesures, shown in Figure 3.9-1, in Ragion 2, and p

" b.. A nominal 9.24 in:5 center 5-center distance between fuel assemblies placed in the storage racks) %d

, y.

[f5.6.1 .---

2 The k,ff.for new fuel for the first core loading stored dry in the

- i spent fuel storage racks sha'il not exceed 0.98 when aqueous foam moderation is l

! } Osumed.

l .

DRAIFAGE

}

5.6.2 The spent fuel storage pool is designed and shall be maintained to ,

! prevent inadvertent draining of the pool below elevation 2040 feet.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1344 fuel assemblies.

5.7 COMP 0NENT CYCLIC OR TRANSIENT LIMIJ 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1. -

c. . A mgmu cc(won a M a"Og K oo hbn quJ. +o I.4ss a.F c,e *F for Sh)(age.-

iA 8egiM1 I..

/

5-7 Amendment No. JZ, 23 CALLAWAY ' UNIT 1

- _ -