ML20128N453
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Dr. F. Findlayson 2350 El Seguand Elvd.
El Sequnou. CA 20245
Dear Dr. Findlayson:
At the request of DR. K. Ara,1. I have enclosed a copy of the following ICCOR reports:
(1) Tecnnical Report 2.1 Ground Rules for the IDCOR Program, (2) Technical keport 3.1 Define Initial Likely Sequececs.
(3) Tact.nical Esport 3.3 Selection of Dominant Sequences - Update, (4) Technical Report 12.1 hydrogen Generation During Severu Cort:
l>amagt Secuencer.,
I (5) Suctask IL.2 hycrcgen Distribution 1c Reactor Contain-ment buildings (Vol. 1),
(6) Suhtask 12.3, Vol. 1 Hydrogen Combustion in Reactor Containment buildings.
(7) Technical Report 14.1A - Key Pnencuenological Models for Assessing Explosive Steam Generation Rates, (E) Technical Report 14.10 - Key Phenomenological Models for Assessing Non-Explosive Steam Generation Rates, (9) Tecnnical Report 15.1A - In-Vessel Core Melt Progression Phenomena, (10) Technical Report 15.2A - Effects of a liypothetical Core Melt Accident on a PWR Vessel with Top Entry Instruments.
(11) Technical Report 15.2B - Depris Coolability, Vessel Penetration, and Debris Dispersal,
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.. (12) Subtask li. 1 Pnenomenological and hoc.elling Lactsrcurd for tne PWh ans SWP. Hestur Coccs (Vol.1), anc
'(10) Subtast 15.3 Final Report on Core-Concrete Interactions.
Sincerely, Christopher Ryaer Accident Source Term Program Office Office of huclear Regulatory kescarch U.S. Nuclear Regulatory Comissicn
Enclosures:
As statec Distribution:
Pis Central File ChROH/ CIRC t.5FF0 Subject File CRyder O
ASTP0/DPA0/RES CRyder:mir 05/3/64 i
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