ML20127K241

From kanterella
Jump to navigation Jump to search
Safety Evaluation Accepting Increased Limitations of U-235
ML20127K241
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 07/08/1975
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127K228 List:
References
NUDOCS 9211200345
Download: ML20127K241 (2)


Text

-. -.

- =.

a,-

. Fi i

}

[

p p.#j.,

f' 1

i 1

r s

o t

_S_AFET.Y. E_ val.tlA_T.I.O.N..S.Y.Ti1E.O.FTICL OF *TCIT A,l: F E. A. CTOR.. P.E.C.U.L..A.T.I_ON t

St.'P.T.O. R.T..i.l.G.. A.hE. NI.Y.T b7. h0

1. 0.T..O F.ACILI.TY.O.P. E. RAT.I.N.G L, ICENSE M.O.. 1)P.R 2 2

~ -

~

l'9RI N h.. STAT [q.[9 9 C % @.

i MON 11CELLC.TC11AT6 CEliERA11fC FLAHT I.TC. K E..T _!.0.._.5_0-263 INTEctUCT10p Ey letter dated Eay 30, 1975 tha nort nern.st at es Tow.'

Coinpany requestea en a-ond9 ant to 1.iceese ro.- !PR-22 for the "ont icella ruelect f*ecer et irt riant.

The request ed cosni s* incroacas tne 0-203 posisession 1itait f ro's 0?m hilo,rars to _'t200 kilov rae.a. - 'Tha incrosed in tt e possession. li:-i t vill cornit. toe inconsee to tema aelivery ot new fuel aloments whicn vill repicco irru iatea f oot olevants achedulea to se re~ovm fram too reactor cord and stored in the spent feel. pool in Octooer 1975.

TVAtt' A1 TON re pla cerer.. of the initial care Cual eat oricinctly Screduled for tue Sprine ot 1976.

1:owever, due to unantiettatet nigo act tvity lovels in tdo reactor coolaut :.na a correspoccice increano or the racioectiva gaseous ef fluent activity, the licensee plans to retual in October 1975.

~

The pre:rature removal ot all reriainine inittal core fuel elerents trior to their planned burnup and replaceevnt with new fuel will result in tne licenseo possessine,3200. ilorrers of t'-235 which exceves the current ly approved possession lir.it o 2300 kilogress.

Thd. net result is an increase at 900 kilograms. in t.no inventury ei un-tiss.oneu C.

The licensee's. planneo course at sction it.rs follows:

i 1.

Temporarily store IP cow Cual eierente in t.. sm :wl : terr e rool vnich ' erosently' cont ains 016 spent tuel aserents.

7 h

orneie-sVRNAMEs>

m DA N rorm AEC.318 (Rev. 9-$3) AECM 0240 tt u s. oovenws.it enmtme orrices iets 4esssa 9211200345 750708

~~~

PDR ADOCK 05000263' P-

-PDR av.i.g g-3-~-'-

q w g W y-ga,g-gyy Pamy4,i-9.=vWW*

9'"'./WMT-r'W'*'

k-T-Nyr

, g-sp > qr y Sr t-~---w'r

  • rg-+

y

^*e-iwv-7 g

1 a:-

I 4

l 1 ~.

l l

~

2.

"er norcrily st ore 11r cew fuel eierents in the new fuel storace vault.

Prior to shutcokn, tuese fuel element s would be transf erred j

to the spent fuel - t e rc e ool.

7here nre r-m !" -

'a elements in the new tuel storare vault.

t 3.

Percove from the core and store the remaining 268 initial fuel elements

_l in the spent fuel pool.

Each time a fuel element is removed from

,I i

the core and stored fu the spent tuel pool a new fuel element will s

be placed in the vacant core thi cell to eilectuate a one-to-one fuel element interchange.

Strict adherence to the one-to-one fuel interchanre is not required for safety since any combination of 740 tuel elenents approved f or use at this tacility can be sately atored in tne spent fuel roof.

Af ter completion of refueline operations, there Vill Le no new tuel eierents stored in the new fuel vault or spent fuel storape pool, and i

there will be 484 irradiated fuel eierents stored in the snent fuel tool.

Ihe cpent tuel stvrape pool is uesicnea to accommoaate 740 tuel elements at iheir riost react ive exposure with an at tendant "ultiptication tactor of less than 0.90 dry or in the floodeu (noinborrico) t ater condition.

The new tuel storare vault is similarNv designed to store 150 new tuel elements with a nultiplication factor of less than u.90 dry and less than 0.95 in the f lood ed (non-borated) water condition.

Consequently, the pronosed number ot fuel eleuents that will be stored at a tir'e in either storace locations will not exceed the design capacit y cna vill rot result in an increased hazard or introuuce c uifterent

}

type of hazard not previously considered at this facility.

CC;'Cin 1GL

'70 hmve concluded. bened on the considerat iens discussed above, tut :

(1) cecause tne c unce aoes not involve a significant increase in the rroDat ili t:, ur consequences 01 accident s previously considered and does n ot. involve a sienificant decrease in a safety margin, the chance aoes not involve a signiticant hazards consideration, (2) there is reasoncble assurance that the health and safety of the cublic vill not 1e endancerad by operation in the proposed nanner, and () r,uch ce t iv tt to wil be c ond uc t ed in compliance with the Conmission's reculat ions ano the issuance of this amendment will not be inimical to the co=on detense and securit y or to the health and safety of the runlic.

e rate:

JUI. 0 6197' I

1 OFFICE >

-.. ~.-~ ~~~----

SURNAME >

--.-~---~~~

DATE>

{

]

Form AEC 318 (Rev. 9-53) AECM 0240 fr v s novsa swr nmm o emes un -a e-m