Published 1986 | Version v1
Report Restricted

Leak behavior through EPAs under severe accident conditions

Description

The leakage behavior of electrical penetration assemblies (EPAs) is being evaluated by varying the penetration type, manufacturer, and hypothetical temperature and pressure accident profile. Nuclear qualified EPAs were procured from D.G. O'Brien, Westinghouse, and Conax. Severe accident sequence analysis was used to generate the severe accident conditions (SAC) for a large dry PWR, a BWR Mark I drywell, and a BWR Mark III wetwell. The EPA manufacturers were matched to the reactor type based on a survey of EPAs used in reactors. The D.G. O'Brien EPA was chosen for the PWR SAC, the Westinghouse was chosen for the BWR Mark III, and the Conax was chosen for the BWR Mark I. The EPAs were radiation and thermal aged to a 40-year service life before the SAC test was conducted. For the D.G. O'Brien EPA SAC test, while there was no detectable leakage during the SAC test, there was a 0.13 scc/sec leak measured during the posttest inspection. For the Westinghouse EPA SAC test, there was no detectable leakage during or after the SAC test. The Conax EPA SAC test is scheduled for completion in July 1986

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86010954.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
SAND--86-0704C

Conference

Title
3. workshop on integrity of containments for nuclear power plants.
Dates
21-23 May 1986.
Place
Washington, DC (USA).

Optional Information

Secondary number(s)
CONF-860507--3.