Integrated analysis of DCH in Surry
An evaluation of the key elements affecting Direct Containment Heating (DCH) was performed for the Surry plant. This involved determining the dominant high pressure core damage sequences, the probability of proceeding to vessel breach at high pressure, the DCH loads, and the containment strength. Each of these factors was evaluated separately, and then the results were combined to give the overall threat from DCH. The maximum containment failure probability by DCH for Surry is 10{sup {minus}3} when considering four base DCH scenarios and using the two-cell equilibrium (TCE) model. However, higher contamination failure probabilities are estimated in sensitivity cases. When the depressurization and containment loads aspects are combined, the containment failure probability (conditional on station blackout sequence) is less than 19{sup {minus}2}. CONTAIN calculations were performed to provide insights regarding DCH phenomenological uncertainties and potential conservatisms in the TCE model. The CONTAIN calculations indicated that the TCE calculations were conservative for Surry and that the dominant factors were neglect of heat transfer to surroundings and complete combustion of hydrogen on DCH time scales.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10135967
- Report Number(s):
- SAND--93-2261C; CONF-931079--22; ON: DE94008870; BR: GB0103012
- Country of Publication:
- United States
- Language:
- English
Similar Records
Risk assessment for the intentional depressurization strategy in PWRs
Assessment of the potential for high-pressure melt ejection resulting from a Surry station blackout transient
Related Subjects
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
C CODES
COMBUSTION
COMPUTER CALCULATIONS
CONTAINMENT
DEPRESSURIZATION
FAILURES
HEAT TRANSFER
HEATING
HYDRAULICS
HYDROGEN
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PROBABILITY
REACTOR ACCIDENTS
REACTOR SAFETY
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR