Containment event analysis for postulated severe accidents: Grand Gulf Nuclear Station, Unit 1

Technical Report · Wed Apr 01 04:00:00 EST 1987

OSTI ID:6429462

Amos, C N; Kolaczkowski, A M

A study has been performed as part of the Severe Accident Risk Reduction Program (SARRP) to investigate the response of a particular boiling water reactor with a Mark III containment (Grand Gulf Unit 1) to postulated severe accidents. A detailed containment event tree for the Grand Gulf Plant has been developed to describe the various possible accident pathways that can lead to radioactive releases from containment. Data and analyses from a large number of NRC and industry-sponsored programs have been reviewed and used as a basis for quantifying the event tree, i.e., determining the likelihood of the pathways at each branch point for a variety of accident sequence initiators. A generalized containment event tree code, called EVNTRE, has been developed to facilitate the quantification. The uncertainty in the results has been examined by performing the quantification three times, using a different set of input each time to represent the variation of opinion in the reactor safety community.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Systems Safety
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6429462
• Report Number(s): NUREG/CR-4700-Vol.4; SAND-86-1135-Vol.4; ON: TI87010288
• Country of Publication: United States
• Language: English

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