Summary of core damage frequency from internal initiators: Peach Bottom

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6907183

Kolaczkowski, A M; Lambright, J A; Cathey, N

Probabilistic risk assessments (PRAs) based on internal initiators are being conducted on a number of reference plants to provide the US Nuclear Regulatory Commission (NRC) with updated information about light-water reactor risk. The results of these analyses will be used by the NRC to prepare NUREG-1150 which will examine the NRC's current perception of risk. Peach Bottom has been chosen as one of the reference plants. The Peach Bottom Atomic Power Station has two boiling water reactor (BWR) units, each with a capacity of 1150 MW(e). The reactors are each housed in a Mark I containment. Peach Bottom Unit 2 analyzed here, was studied before as part of WASH-1400. A number of plant features tend to be important in determining the nature and frequency of the core melt scenarios for Peach Bottom. These features include the recent above-average diesel generator performance history, the single emergency service water system for both units, the numerous emergency core cooling systems, recent procedure modifications and the low volume containment.

• Research Organization: SAIC, Albuquerque, NM
• OSTI ID: 6907183
• Report Number(s): CONF-861102-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 53; Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PEACH BOTTOM-2 REACTOR
REACTOR CORE DISRUPTION
RISK ASSESSMENT
PROBABILITY
ATWS
AVAILABILITY
CONTAINMENT SYSTEMS
ECCS
ELECTRIC GENERATORS
FAILURES
OUTAGES
PERFORMANCE
REACTOR SAFETY
RELIABILITY
US NRC
ACCIDENTS
BWR TYPE REACTORS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
NATIONAL ORGANIZATIONS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled