RELAP5/MOD2 analysis of a postulated cold leg SBLOCA'' simultaneous to a total black-out'' event in the Jose Cabrera Nuclear Station
Technical Report
·
OSTI ID:5210857
- Union Electrica, SA, Madrid (Spain)
Several beyond-design bases cold leg small-break LOCA postulated scenarios based on the lessons learned'' in the OECD-LOFT LP-SB-3 experiment have been analyzed for the Westinghouse single loop Jose 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 Engineering 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 in. RHRS charging line, the 2 in. pressurizer spray, and the 1.5 in. 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.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Union Electrica, SA, Madrid (Spain)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5210857
- Report Number(s):
- NUREG/IA-0075; ON: TI92014259
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5/MOD2 analysis of a postulated ``cold leg SBLOCA`` simultaneous to a ``total black-out`` event in the Jose Cabrera Nuclear Station
Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station
Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station
Technical Report
·
Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:10146143
Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station
Technical Report
·
Tue Jun 01 00:00:00 EDT 1993
·
OSTI ID:10164145
Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station
Technical Report
·
Tue Jun 01 00:00:00 EDT 1993
·
OSTI ID:7368459
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
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ACCIDENTS
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COMPUTER CODES
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EMERGENCY PLANS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
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THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZORITA-1 REACTOR