ML20141L942: Difference between revisions

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| number = ML20141L942
| number = ML20141L942
| issue date = 02/23/1977
| issue date = 02/23/1977
| title = Informs That 770121 Ltr Provided to Members of ACRS for Consideration
| title = Informs That Provided to Members of ACRS for Consideration
| author name = Libarkin M
| author name = Libarkin M
| author affiliation = NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)
| author affiliation = NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)
Line 12: Line 12:
| case reference number = FOIA-91-282
| case reference number = FOIA-91-282
| document report number = NUDOCS 9203270240
| document report number = NUDOCS 9203270240
| title reference date = 01-21-1977
| package number = ML20091A092
| package number = ML20091A092
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE

Latest revision as of 08:29, 12 December 2021

Informs That Provided to Members of ACRS for Consideration
ML20141L942
Person / Time
Site: Oyster Creek, Three Mile Island
Issue date: 02/23/1977
From: Libarkin M
Advisory Committee on Reactor Safeguards
To: Russo S
AFFILIATION NOT ASSIGNED
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203270240
Download: ML20141L942 (1)


Text

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o February 23, 1977 . j.: g 2

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% ** s Mr. Steven P. hi.co '

248 Washington Street P. O. Dax 10f,0

' Ibm River, ikv Jersey 08753 De:r Mr. Rissa:

I Your letter of January 21, 1977, has been provided to nembers of the ACiG for their consideration. lbwever, the purpose of the Subcoruittee meeting on January 29, 1977 and the full Cocnittee sceting on February 10-12, 1977 wa:: conslieration of a set of mathermtical F03e18 proposej

by the LXXO!1 Co
many for use in evaluating the performance of emergency core coolirn systemc in plants of the type (non jet-ptrg, BWRs) repre-sented tv/ tne 0/ater Creek design, in which EXXON fuel may be used in whole or in pcrt. 'Ibe review dji not ertend to the actual operation of a.r, specific plant althoryh som calculations utilizira input parameters -

typic:i1 of the Oycter Creci: plant were evaluated. I have attached a copy of the rep 3rt to the imC which resulte3 frorr. this review.

5ine; your remrka dealt primeri.ly wIth the piilosophy end effeetiveness of the liac's rr forcement progran, we have sleo tranarnitted than to the Officer of Nuclear Reactor Roaulation, and Inspection and Enforcecnt w: ich are respancicle for this aspect of the regulatory program.

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11. ii. Libarkin, Assistant

-Executive Director for l- Project Review Attactrient c-I' Recor t on EXXD:t thrlear Cove.ny l MG+-Lased lion-Jet Pug) Boilin]

V, ster lletetor ECC3 t' valuation j  %: Gel date$ 2/10/77 1 cc- E. G. Case , MiU' V. 6tcllo. DX:

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