ML19224B902
| ML19224B902 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/11/1979 |
| From: | Serpan C NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Tong L NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 7906270172 | |
| Download: ML19224B902 (1) | |
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May 11,1979 t
MDiO R'iDUtt FOR:
L. S. Tong, Assistant Director for Water Reactor Safety Research FROM:
C. Z. Serpan, Jr., Chief Metallurgy & Materials Researt:h Branch SU3 JECT:
M&!!R BRA'iCH ACTIVITIES 0:1 T14I-2 FOR WEEK CiDING 5/12/79 A qualitative evaluation of the failure potential of the THI-2 reactor vessel was nade this week. Taken into consideration were the temperature of the cold-leg injection ECC, the vessel temperature, the pressure I
levels and the times at temperature and pressure during the accident and let-down sequences.
It was concluded that the most severe loading of the vessel occurred about three hours into the accident,when the vessel pressure was raised to 2150 psi while the HPI was till1 mderway.
The loading here was analytically insufficient to cause crack initiation or extension, and there is no evidence that any cracking did occur.
At no other time during the accident was the vesul loading as severe as at this tire, nor is it now. More detailed, aalytical calculations of the accident can be developed if considered necessary.
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C. Z. Serpan, Jr., Ehief j
Metallurgy & Materials Research Branch DIST.
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