ML19322C535
| ML19322C535 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Arkansas Nuclear, Crystal River, Midland, Crane  |
| Issue date: | 04/07/1978 |
| From: | Dunn B, Rosalyn Jones BABCOCK & WILCOX CO. |
| To: | BABCOCK & WILCOX CO. |
| References | |
| TASK-TF, TASK-TMR PSC-10-78, NUDOCS 8001170864 | |
| Download: ML19322C535 (2) | |
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epril 7, a,0.0/.-ft2'small break' analysis at pu=p discharge-on the S)."JD plant was con-lted. (Results'show substantial core uncovery tj TO Tout In:rLIDGI 1: RE: AWARI?
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I AFFICitC CCxTF8CI: ( U:TCHit at.at AE0 LCCATICK) hec 1, 2, and 3 (Duke Power Corp.), Crys:al River 3 (florida Power Corp.), n:I-1
$. Ed.),s nII-2 -(JC?&L), ANO-1 (Arkansas P&L), Midland 1 & 2 (Consumer's Pover) l IPTIC% OF :lltif CCt CtfulDtrTIFT AFf t:Tt3 CCHFC:lX T( ). :T:TCH(:) 02 ACTfYlif/ UPPLitt. At3 IkPACT cz f CF PLAxi CPttaflos:
l small breaks at the pu=p discharge on the 177-Ff Lowered Loop Plants (iden:ified he), the li?I pucpc are inadequate to control the accident to the criteria of 2
EFR 50.46.
The analysis perforced for a 0.04-f break a: the pump discharge bs core uncavery starting at %1700 seconds.
The mixturc level in the core at o seconds is icss than 4.0 f t.
This level is inadequate ter maintain cladding cratures below 2200F.
Long.:cra cooling will not be established by the E?I
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until %3200 seconds.
Thus, the inadequate level at 2400 seconds is not even
.tuinieu= level that vill be reached during the accident.
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'CC C0tstCTitt ACT804 COMPLtit3/TO :t lAlilAftD fully Q/A the results.
3dentify and analy e hardware fixes (it is expected ths: crocc-connecting each
!?I to all four cold legs will result in an acceptable fix).
k2 port and document results to the NRC.
8001170 h s
B' tt uit ECCS Analysis. Fluid Systems Analvsis. Plant Inte: ration l
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.P. GE!!ERATI0tl GROUP I
DISTRIBUTION J. H. TAYLOR - MANAGER,. LICENSING (2817) 8 b M [-
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PSC 10-78 205 T4.4 r Re Date PRELIMINARY REPORT OF SAFETY CONCEPli PS,C 10-78 lm...............................;......,.
DISTRIBUTION R.
C. Jon,es.
J. C. Deddens C. D. Russell B. M. Dunn J. J. Stewart R. C. Luken A. L. MacKinney '
G. M. Olds-J. T. Janis J. P. Jones D. H. Roy G. T. Fairburn W. A. Cobb
' A. H. Lazar F. J. Levandoski B. A. Karrasch
. E; G. Ward E. R. Kane B. B. Cardwell L. J. Stanek H. A. Eciley D. W. Berger J. D. Phinney D. Mars Record Center In accordance with procedure NPG-1707-01, "P'rocessing of Safety Concerns," I am forwarding a reported concern relating to sna11 breaks at the pump discharge on the 177FA Lowered Loop Plants.
PSC 10-73 has been assigned as'the PSC number for this case.
A; preliminary indication;'issthatzthis concern will be recortable
's now i
Effort ita the-NRC under the-requirements iof 10XCFR 21.
in progress on preparing an evaluation and on reconnendations for When my staff has, completed its possible corrective action.
ovaluation report, I will communicate their findings to you.
of contact within Licensing on this case is H. A. Bailey,.
The point Ext. 2673.
JHT:dsf Attachment
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