RELAP5/MOD2 Analysis of a Postulated "Cold Leg SBLOCA" Simultaneous to a "Total Black-Out" Event in the José Cabrera Nuclear Station (NUREG/IA-0075, ICSP–JC–SB3–R)
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Date Published: April 1992
Union Electrica Fenosa S.A.
c/Capitin Haya, 53
28020 Madrid, Spain
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Thermal-Hydraulic Code Assessment
and Application Program (ICAP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Several beyond-design bases cold leg small-break LOCA postulated scenarios based on the "lessons learned" in the OECD-LOFT LP-SB-3 experiment bave been analyzed for the Westinghouse single loop José Cabrera Nuclear Power Plant belonging to the Spanish utility UNION ELECTRICA FENOSA, S.A.
The analysis has been done by the utility in the Thermal-Hydraulic & Accident Analysis Section of the Enginneering Department of the Nuclear Division.
The RELAP5/MOD2/36.04 code has been used on a CYBER 180/830 computer and the simulation includes the 6" RHRS charging line, the 2" pressurizer spray, and the 1.5" CVCS make-up line piping breaks.
The assumption of a "total black-out condition" coincident with the occurrence of the event has been made in order to consider a plant degraded condition with total active failure of the ECCS.
As a result of the analysis, estimates of the "time to core overheating startup" as well as an evaluation of alternate operator measures to mitigate the consequences of the event have been obtained.
Finally a proposal for improving the LOCA emergency operating procedure (E-1) has been suggested.