Severity of radionuclide releases: A comparative study of Mark-I containments

Conference · Fri Jan 01 00:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7129176

Khalil, Y F ^[1]; Jondle, D D ^[2]

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1. Northeast Utilities Service Co., Berlin, CT (United States)
2. Detroit Edison, Newport, MI (United States)

Generic Letter 88-20, Supplement No. 1, issued by the U.S. Nuclear Regulatory Commission (NRC) requested all licensees holding operating licenses and construction permits for nuclear power reactor facilities to perform individual plant examinations (IPES) of their plants for severe accident vulnerabilities and to report the results to the commission. The NRC provided guidance on preparing the IPE document in NU REG-1335 as well as analyses for five reference plants in NUREG-1 150. Peach Bottom unit 2 is the NRC's reference plant for boiling water reactors (BWRS) with Mark-I containments. Northeast Utilities submitted the Millstone unit I IPE report4 in March 1992, and the Fermi-2 IPE submittal was in September 1992. The purpose of this work is to compare Millstone unit I [a 2011-MW(thermal) BWR-3 General Electric (GE) plant] to Fermi-2 [a 3430-MW(thermal) BWR-4 GE plant] with respect to potential containment failure modes (early, late, and no failure) and severity of radiological releases for accidents that extend beyond the design bases. The emphasis of this study is on the back-end analysis [level-2 probabilistic risk assessment (PRA)] of the IPE studies, Refs. 4 and 5, respectively. In addition, reference is made to the Peach Bottom unit 2 [a 3293-MW(thermal) BWR-4 GE plant] results (from NUREG-1150) as deemed appropriate.

• OSTI ID: 7129176
• Report Number(s): CONF-931160-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 69; Conference: American Nuclear Society (ANS) winter meeting, San Francisco, CA (United States), 14-18 Nov 1993; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENRICO FERMI-2 REACTOR
COMPARATIVE EVALUATIONS
RISK ASSESSMENT
MILLSTONE-1 REACTOR
CONTAINMENT
FAILURE MODE ANALYSIS
RADIOACTIVITY
REACTOR SAFETY
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
EVALUATION
POWER REACTORS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled