ML20040C498

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Forwards Revised Description of Loft Tests Applicable to Degraded Core Cooling Rule & Revised Comparison Schedule
ML20040C498
Person / Time
Issue date: 12/22/1980
From: Lisa Sullivan
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Shao L
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML19295F938 List:
References
FOIA-81-381 NUDOCS 8201270736
Download: ML20040C498 (6)
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DEC 22.1980 HEMORANDUM FOR:

Lawrence C. Shao, Acting Director Division of Reactor Safety Research Office of Nuclear Regulatory Research FROM:

L. Harold Sullivan, Acting Assistant Director for Water Reactor Safety Research Division of Reactor Safety Research

SUBJECT:

REVISION TO IIRSR ACTIONS PLANNED TO SUPPORT DEGRADED CORE RULEllAKING Enclosed are a revised description of LOFT tests applicable to the degraded core cooling rule and a revised WRSR comparison schedule. These revisions provide infomation on LOFT tests scheduled beyond the final rule

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date but thich would provide infomation pert 1nant to the tvle if one or both schedules could be modified.

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L. Harold Sullivan, Acting' Assistant Director for Water Reactor Safety Research Division of Reactor Safety Rescarch

Enclosures:

As stated cc: WRSR Branch Chiefs, w/encis:

DISTRIBUTION l

Subject Chron Circ R.R.Landry G.D.McPherson C. Johnson

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Branch R/F l

R.R.Landry R/F 8201270736 811009 PDR FOIA t

CONNER 81-381 PDR L

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l Updated 12/19/80 o

WRSR M TIO.NS PLANNED TO SUPPORT DEGRACED CORE RULEMAKING Name of Task: LOFT Responsible Staff Member and Branch:

G. D. McPherson LOFT Research Branch, Division of Water Reactor Safety Research Description of Action Planned:

LOFT will perform one test applicable to the degraded core cooling rule making in FY-1981 and two applicable tests in FY-1982. The first test, L8-2, is to be run in conjunction with an intermediate size break test.

L5-1.

The L8-2 test will be run with unpressurized fuel and could result in moderate fuel damage. The second test, L2-5, is to be a large break LOCA run at conditions simulating a loss of offsite power at a large PWR with best-estimate fuel conditions. This test is not expected to result in fuel damage, thus serving as a baseline for severe fuel damage tests and as a measure of conservatism in the licensing fuel models. A second f

large break LOCA test, L2-6, planned for mid FY-1982 will be run in such a manner as to cause extensive clad ballooning and burst. Since LOFT uses 15x15 fuel assemblies, this test will provide information on burst and balloon patterns and fuel assembly flow blockage that cannot be obtained in small size fuel arrays. A part of this test will include examination of fuel pellet relocation and pellet debris wash-out through the burst cladding. All tests will provide data on incore heat transfer.

Beyond FY-1982 three tests, L8-3,4, and 5, are planned which will lead to severe fuel and core damage. The tests will include both slow and fast cladding heat-up rates with pressurized fuel.

Schedule Milestones:

The current test schedule is for L8-2 in August 1981, L2-5 in January 1952, L2-6 in May 1982, L8-3 in July 1983. L8-4 in February 1985, and L8-5 in November 1985.

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FY 1981 PROGRAM BRIEF PROGRAk$~ASTR k

TITLE: Themal-Hydraulic LMFBR CONT:

FIN NO: A-3024 Safety Experiments CONTRACTOR: BNL SITE: Upton i

1 STATE: New York e

NRC TECHNICAL MONITOR:

R. W. Wright S

PRINCIPAL INVESTIGATOR:

T. Ginsberg OBJECTIVE:

Perfom experiments on and develop phenomenological models of themal hydraulic phenomena of importance to LMFBR and LWR safety assessment in

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the areas of post-accident core debris behavior and transition-phase behavior with emphasis on fuel freezing and plugging.

BUDGET ACTIVITY:

60192001 FY 1981 SCOPE:

FY 1981 OBLIGATION: -300 K The work scope description provided below constitutes,.in part, a change in scope from previous guidance. The following indications of priorities are given.

1.

Continue survey of existing models and experiments applicable

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to fuel relocation dynamics. Continue modeling effort for multi-phase solidification with wall melting. Develop a comprehensive test matrix, 1

perform preliminary tests and report results.

2.

Complete analysis of " steam-spike" problem applicable to LWR disrupted

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core accidents including experience gained at metal processing industries.

Initiate and complete preliminary analysis of processes and phenomena g

involved including a sensitivity analysis of " steam spike" to conditions t

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prevalent in disrupted core cooling.

i 3.

Prepare and issue a brief, informal report on an assessment of the state-l of-technology models of themal hydraulic phenomena in melt-concrete 1

interactions, noting areas of major uncertainty and possible separate effects tests for their resolution.

Impact of uncertainties on accident analysis should also be includqd.

4.

Provide NRC/ASTR with technical consultation in the themohydrodynamic j

area as requested and continue assessment of foreign and domestic research I

in the area.

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.6,0 ROUTlHG AND TRANSMITTAL SLIP

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disapprova s, clearances, and similar actions j

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~ysj6 OPTIONAL FORM 41

.ee-to-easse-a nas-i.a 3641 101 0*?',M.c,,........

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