ML19220C637

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Discusses Prelininary Calculations for Outside Limits of Possible Core Damage.Believes 25-35% Core Damage Near Ctr Is Upper Limit at 1.8 Hours Transient
ML19220C637
Person / Time
Site: Crane 
Issue date: 04/06/1979
From: Beckner W
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML19220C630 List:
References
NUDOCS 7905110363
Download: ML19220C637 (2)


Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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'* g W ASHINGTON, D, C. 20555 APR 6 1979

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MEl10RANDUM FOR: File William D. Beckner Separate Effects Research Branch FROM:

PRELIMINARY CALCULATIONS OF THREE

SUBJECT:

CORE DAMAGE to Initial attempts have been made to bound the po id with high exists that the core was covered with saturated flu the core.

At 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the main coolant pump wa flow rates.

d Superheat in the hot leg and subcooling in the cold leg w this time.

This suggests little or no coolant as well as a pressure drop.

flow and an at least partially voided core.

To bound the damage, an assumption of a completelg* voide (lower limit witn a heat transfer coefficient of 3.0 Btu /hr-ft._ F Under these based on calculations of Y. Y. Hsu on 4/6/79).

Fuel assumptions and making use of information developed by the 4/4/79),

Behavior Research Branch (letter, Marino b ut 25% of This represents about 11-13 Kwt/ft would be damaged.

This should represent a good u_om the core volume near the center.

bound on core damage,at this time.

During later time periods (8-14 hours), similar dry conditio could have lasted for significantly longer periods and steamA Up to 40% of the core volume temperatures may have been higher.

10 Kw/f t cauld also have been damaged.

could have been damaged.

f These numbers are scoping calculations based on a lim information and some assumptions. Updated calculations will be perfo damage was possible.

information becomes available.

L!dba b $<W William D. Beckner Separate Effects Research Branch Division of Reactor St if Research cc: see next page 7905110 3 4 3 gg jjo