ML20141K860

Discusses ACRS 126th Meeting W/Util to Discuss Licensee Request to Increase Max Power Level of Plant from 1,600 to 1,690 Mwt.Subcommittee Meeting Scheduled for 701111

ML20141K860
Person / Time
Site:	Oyster Creek
Issue date:	10/20/1970
From:	Fraley R Advisory Committee on Reactor Safeguards
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20091A092	List: IA-91-282, Forwards Written Statement Submitted by Sp Russo for ECCS Subcommittee Meeting on 770129,for Info.W/O Encl ML20141K026 ML20141K047 ML20141K056 ML20141K063 ML20141K066 ML20141K070 ML20141K076 ML20141K082 ML20141K091 ML20141K095 ML20141K121 ML20141K137 ML20141K141 ML20141K153 ML20141K163 ML20141K175 ML20141K185 ML20141K190 ML20141K359 ML20141K365 ML20141K368 ML20141K372 ML20141K375 ML20141K379 ML20141K382 ML20141K386 ML20141K390 ML20141K395 ML20141K398 ML20141K402 ML20141K406 ML20141K408 ML20141K415 ML20141K418 ML20141K423 ML20141K426 ML20141K432 ML20141K436 ML20141K441 ML20141K618 ML20141K620 ML20141K625 ML20141K626 ML20141K630 ML20141K633 ML20141K635 ML20141K637 ML20141K641 ML20141K643 ... further results
References
FOIA-91-282 NUDOCS 9203250330
Download: ML20141K860 (1)

Text

_ . _ _ _ . . _ _ . . . _ _ . _ . . _ _ _ . _ . _ _ _ _ _ _ . _ _ . . _ . . . . _ . _ . _ . .

f 137 t

g October 20, 1970

,, y f<

.;-'I Peter A. Morris, Director Division of Reactor Licensing OYSTER CREEK During its 126th meeting the ACES sonsidered the application by Jersey Central to increase the maximum power level of. the Oyster l Creek station from 1600 to 1690 MWt. At the conclusion of that meeting the applicant was informed that the Committee was unable ll

)'

to render a decision. To aid the Comaittee in this review, the Regulatory Staff is requested to prepare a brief eupplemental report evaluating the adequacy of the cu rent emergency cerce ecol--

.ing capabilities of the_0yster Creek Station utilizing current

- experimental information and analysis. The evaluation should include peak and average fuel clad temperatures at the time core

-spray is initteted and the highest peak and everage clad temperatures '

predicted for_the accident. It would be useful to have a curve showing the percentage of the core that exceeds a given temperature

-(temperature vs _ percent of fuel clad) .

In addition.to-the-supplemental report the Regulatory Staff should L_p - be prepared to discuss. the applicability of recent TLECHT test

' resul.*,sto Oyster Creek, how the level sweli phenomenon appites, how the fire. protection system could be utilised for core cooling,

~ and _how actual liquid redwaste releases compare to -technical 5,ecif t-

- cation limits. _ It will also be helpful to review the -considerations that' led to the decision to not install a third diesel generator.

TheLCommittee recognises _that the Regulatory Staff will be pressed l

for time to complete a report covering these points and it will be

~ satisf actory if the report is available to the Comunittee by November

,] 10.-1970.

g

• A Suh..oenittee meeting is scheduled for Wednesday, November 11, 1970.

__ j A.echedule and agenda will be - forwarded tc you later.

\; '

Original Sigosql R. F. Fraley ,

R. F. Frr.Tey g p', ,7 ,

l. [ ,,i.g r.

v Executive Secretary

.ggp A g,f f f e. , , m -

4 . e Ft. led: Oyster Creek Record Kate: Based on discussions 2sith i

~~' : * ^

ouva and ucud.ic un 10/19/70 .' '

omer > . . ACRS ,_ ,,_ ,,,,, _ _ , _ ,,, ,_, _ _ , , , _ _ _ _ ,

M i m g,;

. TC.g:.8dR.FF:bj... _ _ _ . . . . . . . . . . . . . . . . . . . . . . . . _ . . . . . . . . . . . . . ._ . _ .

t wer ,.

t

.N m W 415(R.v.D.68) u,s sovtanuent renemns caruz de-o messe , .

h(

J l 9203250330 910807 Mb f ng b PDR FDIA P'*

p4 DEKOK91-282 PDR a

_ . _ . _ _ . _ __ _ ,