Pretest analysis document for Test S-FS-7

Technical Report · Sat Jun 01 00:00:00 EDT 1985

OSTI ID:5278420

Hall, D G

This report documents the pretest calculations completed for Semiscale Test S-FS-7. This test will simulate a transient initiated by a 14.3% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represent normal operating conditions for a C-E System 80 nuclear power plant. Predictions of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The results of a RELAP5/MOD2/CY21 code calculation indicate that the test objectives for Test S-FS-7 can be achieved. The primary system overpressurization will occur but pose no threat to personnel or to plant integrity. 3 refs., 15 figs., 5 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5278420
• Report Number(s): EGG-SEMI-6919; ON: TI85017486
• Country of Publication: United States
• Language: English

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