NUREG-1150 risk assessment results
The methodology developed in support of the US Nuclear Regulatory Commission's (NRC's) evaluation of severe accident risks in NUREG-1150 is noted. This paper discusses the results. The principal technical analyses for NUREG-1150 were performed at Sandia National Labs. under the Severe Accident Risk Reduction Program and the Accident Sequence Evaluation Program. The analyses have been completed so far for four reference plants: (a) a pressurized water reactor (PWR) with a dry, subatmospheric containment (Surry Unit 1), (b) a PWR with an ice condenser containment (Sequoyah Unit 1), (c) a boiling water reactor (BWR) with a Mark I containment (Peach Bottom Unit 2), and (d) a BWR with a Mark III containment (Grand Gulf Unit 1). A fifth NUREG-1150 plant, a PWR with a large, dry containment (Zion Unit 1), has been evaluated separately by Brookhaven National Lab. Sample risk results for one of the plants (Surry) are presented. The results for Sequoyah, Peach Bottom, and Grand Gulf are broadly compared with those for Surry.
- Research Organization:
- Sandia National Lab., Albuquerque, NM
- OSTI ID:
- 5624684
- Report Number(s):
- CONF-870601-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 54; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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