ML20100F366
| 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 | |
| ML20100F143 | List:
|
| References | |
| FOIA-95-389 NUDOCS 9602210229 | |
| Download: ML20100F366 (3) | |
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"" O E i W e* @ !f' wassiuorou.a.c. aosia September 9, 1971
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Mr. James R. Schlesinger
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j Chairman l
-Atomic Energy Commission
" Washington,"D.
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Dear Mr. Schlesinger:
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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 from you on the following points:
., q 1)
Will the reanalysis of the ECCS in operation ~at
,N-Oyster Creek, under construction'at Salem, and h
(i at other plants being planned for New Jersey in
(, ir s
.e Island,beperformedonasmallsemi-scale'reactot}
Union County, at Forked River, and at Newbold
.v. N 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 y'y /\\
l
- General. Electric Company based?
Small semi-scale
.)
mode'.. tests, theoretical calce".ations,. testing of )
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actual equipment, or a combination of these three?/
pmallsemi-scaleexperimentsandlargepowerreactors,Q If there are significant differences between the 3) are there any other models more similar in construction
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-andl performance to large reactors upon which the AEC
.can' base its reliance?
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9602210229 960129 PDR FOIA DEKOK95-389 PDR y
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l Y.-4. ; 9 ',.Mr_.: (Jamis i R._ Sch5 singer,
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Se'pt' ember 9, 1971 l
4 Page_Two~
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Since it is my understanding that there have bcen errors experienced in estimating fuel-cladding fc temperatures,given.the,critienl-importanceofthe,.)I 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 v.*&aJeommissionisey authoris4 full, powerseposetion ;-
1 7
of the-reactor (if a limitation ~were im' posed) for[ p~,:
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- limited' period"..What type of administrative 5
, procedure would be employed by.the Commission in,,
this event?
~
t 6)
Given the AEC's defense-in-depth concept, istherehcE any other system present in the normal reactor to
~
reduce the temperature of a molten core, if the l'
ECCS fails?
7)
If'the primary assurance of react,or safety in a f,
j nuclear power plant is by " correctly designing, be constructing and operating the reactor", is there
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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-G'!
gency core cooling systems could be improved as-I' N,..
opposed to a July 1,1974, limit?
~ '
In closirig, let-me state that the. doubts on the reliability
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,of.the ECCS raised by these test failures should cause the AEC to 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 l.-
Again, I wish;to. emphasize that your assistance in. answering. l i
these qu'estions will be greatly appreciated.
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t,d' september 9, 1971:
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~Page Three' 1
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With best wishes, e
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a Sin /^cerely,',
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Harrison A. Wil1[ams, Jr.
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