ML19261E971
| ML19261E971 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/20/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19261E968 | List: |
| References | |
| NUDOCS 7910171025 | |
| Download: ML19261E971 (1) | |
Text
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a SUPPLDENT TO SAFETY EVALUATION TilREE MILE ISLANI), UNIT 1 (CONTAINMENT SYSTEMS)
DOCKET N0. 50-289 SUBCOMPART'ENT PRESSURE ANALYSIS The applicant has presented the results of calculations of pressure differentials across walls of equipment compartments inside the con-tainment. We have performed similar calculations that have led to results which are in reasonable agreement with the applicant's computed values.
2 For the reactor cavity compartment assuming a 8.55 ft coolant pipe rupture we have calculated a differential pressure of about 141 psi, whereas, the applicant computed 160 psi. The design value was specified as 160 psi.
The applicant calculatec a peak differential pressure of 15.0 psi for a double-ended hot leg break within the steam generator compartment. Our evaluation indicated a peak differential pressure of about 12 psi. The des 12n value was specified as 15.0 psi.
Based on our eva~
- ion of both the reactor cavity and the steam generator compartments, we conclude that the design pressures of the subcompartments are acceptable.
1483 434 "e w eme e,.
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