Containment response to a small main steam line break
- Pennsylvania State Univ., University Park (USA)
The purpose of the work described in this paper was the development of a dry-well temperature profile for 100 days following a small steam line break inside primary containment. The results of this study will be used to justify a plant-specific dry-well temperature envelope for equipment qualification that is less severe than that recommended by General Electric (GE) and the US Nuclear Regulatory Commission. The current dry-well temperature envelope used for equipment qualification at certain boiling water reactor (BWR)/4 MK I plants specifies a constant dry-well temperature of 366.5 K (200{degree}F) after 1 day. The results of CONTAIN calculations performed on a BWR/4 MK I plant were compared to the existing qualification envelope and a new curve was developed. The results of this study indicate the usefulness of plant-specific analysis for this particular scenario. The revised temperature profile predicts lower containment temperatures than the conservatively high GE profile; therefore, equipment that was qualified using the old profile can now be qualified for longer periods of time, and previously unavailable equipment may now be qualified. This revised equipment availability may alter current emergency operating procedures for this particular transient.
- OSTI ID:
- 6372947
- Report Number(s):
- CONF-900608-; CODEN: TANSA; TRN: 91-008257
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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