ML20100F366

Requests Results of Reanalysis of ECCS Failures as Soon as Practicable

ML20100F366
Person / Time
Site:	Oyster Creek
Issue date:	09/09/1971
From:	Williams H SENATE
To:	Schlesinger J, The Chairman NRC COMMISSION (OCM)
Shared Package
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References
FOIA-95-389 NUDOCS 9602210229
Download: ML20100F366 (3)

Text

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September 9, ,

1971

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l Mr. James R. Schlesinger .

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Chairman l -Atomic Energy Commission

" Washington,"D. C.. "2054'5 -

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Dear Mr. Schlesinger:

~

This is to-acknowledge the response of former Chairman  ;

Seaborg to my letter of June 24th, in which I requested infor-

. mation on the effect of emergency core cooling system (ECCS) failures on certain nuclear powered reactors. ,-

In regard to the reanalysis being required of the emer-

. gency core cooling systems at Oypter Creek and at other plants being constructed or planned for New Jersey. I would appre-ciate being informed of the results of the reanalysis as soon as is practicab.le. *

• ,In that same vein, I would also appreciate a response

., q from you on the following points:

Will the reanalysis of the ECCS in operation ~at 1)

- ,N- Oyster Creek, under construction'at Salem, and h s

at other plants being planned for New Jersey in ( , ir (i

.e

.v. N Union County, at Forked River, and at Newbold Island,beperformedonasmallsemi-scale'reactot}

mockiip similar to those used in the Idaho tests?j/

2) Upon what was the preliminary information on the . gf Oyster Creek plant which the AEC received from /\

- General. Electric Company based? Small semi-scale y'y

.)

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.. mode'.. tests, theoretical calce".ations,. testing of ) /f',

actual equipment, or a combination of these three?/

3) If there are significant differences between the

.. ". pmallsemi-scaleexperimentsandlargepowerreactors,Q are there any other models more similar in construction

~g*r? ' -andl performance to large reactors upon which the AEC

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.can' base its reliance? h' /'- /s ,

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4) Since it is my understanding that there have bcen errors experienced in estimating fuel-cladding temperatures,given.the,critienl-importanceofthe,.)I fc Ti -

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ECCS whose effectiveness;is now suspect, should j nuclear power reactors be permitted to produce. ",,

3

. theii normal electrical power output? _  ;

15) On page 2 of your July 26th letter, you state that

• 1' v.*&aJeommissionisey authoris47 full, powerseposetion ;-

• " 1 of the-reactor (if a limitation ~were im' posed) for[ p~ ,:

• limited' period". .What type of administrative , ,

5

~

, procedure would be employed by.the Commission in,,

. this event? -

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6) Given thesystem AEC'spresentdefense-in-depth in the normalconcept, reactor toistherehcE any other

~

reduce the temperature of a molten core, if the l'  ;

. ECCS fails?  ;

7) If'the primary assurance of react,or safety in a j nuclear power plant is by " correctly designing, f, constructing and operating the reactor", is there be '

} ,

also"a process of extensive testing of all systems I

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before normal operations are allowed?

I '

8) 'What is the earliest possible time that the emer-gency core cooling systems could be improved as- G'!

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- N ,. . opposed to a July 1,1974, limit? ., .

~ '

! .(. In closirig, let- me state that the. doubts on the reliability }

} ,of.the ECCS raised by these test failures should cause the AEC to l postpone indefinitelys administrative procedures to modify the .  !

' ()

L .

license of Jer.sey Central Power and Light Company to operate the ,;

_ Oyster Creek Nuclear Powe'r Plant Unit No. 1 at increased power l levels, until full-scale tests can be' conducted.to demonstrate

. the effectiveness of safety features.

'. l Again, I wish;to. emphasize that your assistance in. answering. l '

l.- . these qu'estions will be greatly appreciated.

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With best wishes, .  !

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, l Sin /^cerely,',

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