ML20141L930

From kanterella
Jump to navigation Jump to search
Responds to Request for Comments on Preliminary Analysis by P Davis of Probability of Catastrophic Accident During Remaining Lifetime of Plants
ML20141L930
Person / Time
Site: Oyster Creek, Crane
Issue date: 11/16/1976
From: Moeller D
Advisory Committee on Reactor Safeguards
To: Paulson G
NEW JERSEY, STATE OF
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203270197
Download: ML20141L930 (1)


Text

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

els 4,

Novenber 16, 1976 uv -

p.51 '

]

i.+

Dr. G. Paulson Assistent Comissioner for Science

!boartrent of Environ ental Protection State of New Jersey Trenton, NJ 08625 Dear Dr. Paulson The Mvisory Comittee on Reactor Safeguards has considered your request i

13r co rents on the preliminary analysis by Mr. Peter Davis of the prob-aallity of a catastrophic accident during the remaining lifetime of the O/ ster Crech plant.

It is unfortunately not possible for the ACIG to provide a datailed review of this study. 14 note, however, that Mr. Davis suggerts that the incorporation of the autocatic recirculation ptrp trip would lead to a substantial reduction in the probability of a core melt following a failure to scram on an anticipated transient.

The ACr:5 has been follosing closely the continuing evaluation of the natter of anticipated transients without scram (A7WS) since the question was raised by this Comittee several years ago. 'Ihe recirculation panp trip feature is included in nost, if not all, of the rwer boillry water reactors in operation or under c:)nstruction, and in March 1976 the ACf6 l

recomended that this feature be implenented promptly on all operatin]

BWA's unless analyses have shwn that such a trip is not required to mitigate the consequences of A'IWS.

We understand that the Jerrey Central Power and Light Company has mido a co nittaent to install such a pup trip unless they are able to provide a convincing de:nonstration that other f eatures. incorporated in this plant Lake this trip unnecessary (see attachnents).

Sincerely yours, Originul ciCnt o kY PADE17. LCILLCl

{ 910 W Dade W. Moeller Q

2 DEKOK91-282 PDR Chaircon Attachmentst X

N.

1) ACES letter to L. V. Gossick March 12, 1976

/

f i

h)-_

AQRS_

2)

Jersey Central Pwer & Li?P t ACR

  • " > * * *- Ccaparr/ lotten Octobc t-4 r.J 9 7 6 ----.- -- ACE
    • =s*

.,-bee t-ACRS -Narerr Staf f-NM --

17 RFF o r_,,,,.

11/16/76 Chrm DWM

    • ve >

S tell.o,_. Den ton,..Boyq d eineman,.

_ gg asiassst? peace =s Onect}sa wpqRII i Form AEC.)l3 (Re.. M)) AECM OW355 AC K g Au5GDC, % g,gp,T e s e. e ae.t es

~

L a.

t

(

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCtt AFI REGUL ATORY COMMIS$10N W ASHING T ON. D. c. 205%

March 12, 1976 Lee V. Cossick Executive Director for Operations

Subject:

PICIRCULATION PDIP TPJP To llELP LIMIT Tile CONSEQUENCES OF AN AWS EVENT IN BWRs i

It has recently come to the attention of the ACRS that not all operating boiling water reactors have installed a recirculation pucp trip to help limit the consequences of an A*NS cvent.

Such a trip was proposed by applicants for construction permita in 1971 end for operating licenses in 1972.

j The Co m.ittee believes that the recirculation pump trip represents a j

substantial ~improvemen't in protection for BWRs and should be icpic-me.nted promptly on all operating LURs unicss analyses have shown that I

such a trip is not required to mitigate the consequences of ATWS.

Picase provide the Coc.ittec with a list of those reactors in operation,

)

or nearinC operation, which do not have such a trip and a schedule for l

installation of this trip on a ticely basis, Sincerely, 1

l Dade W. }!oclier Cheirman 4

e O

y

-h

_t 4' -~' i }ll _' fi*",

i

, _ _x

.