ML19261E963
| ML19261E963 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/17/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19261E961 | List: |
| References | |
| NUDOCS 7910171018 | |
| Download: ML19261E963 (1) | |
Text
SUPPLEMENT TO SAFETY EVALUATION THREE MILE ISLAND, UNIT 1 (CONTAINFENT SYSTEMS)
DOCKET NO. 50-289 The applicant has analy::ed the ability of the containment to withstand the peak pressure which might be encountered during a loss-of-coolant accident. To ensure that the most severe breux size and location were selected, the applicant performed analyses for a spectrum of breaks at various locations.
The break producing the highest containment pressure was a 7 ft split of the pump suction piping which resulted in a containment pressure of about 50 psig.
The design pressure is 55 psig. We have reviewed the assumptions used by the applicant in this analysis and performed confirmatory analysis for this break.
The applicant calculated the mass and energy release rates to the containment using the CRAFT code for both the blowdown and reflood periods. We have reviewed the assumptions used in this code and found them to be reasonably conservative.
In our analysis of containment pressure, we used the mass and energy release rates calculated by the applicant for the blowdown period.
During the reflooding period, however, we used the FLOOD-2 code to predict the mass and energies to the containment. We calculated containment pressure using the CONTD2T code and calculated the same centainment pressure.
We, therefore, conclude that the design pressure of 55 psig is acceptable.
1483 324 msnO/T
.