Simplified containment event tree analysis for the Sequoyah Ice Condenser containment
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
An evaluation of a Pressurized Water Reactor (PWR) ice condenser containment was performed. In this evaluation, simplified containment event trees (SCETs) were developed that utilized the vast storehouse of information generated by the NRC's Draft NUREG-1150 effort. Specifically, the computer programs and data files produced by the NUREG-1150 analysis of Sequoyah were used to electronically generate SCETs, as opposed to the NUREG-1150 accident progression event trees (APETs). This simplification was performed to allow graphic depiction of the SCETs in typical event tree format, which facilitates their understanding and use. SCETs were developed for five of the seven plant damage state groups (PDSGs) identified by the NUREG-1150 analyses, which includes: both short- and long-term station blackout sequences (SBOs), transients, loss-of-coolant accidents (LOCAs), and anticipated transient without scram (ATWS). Steam generator tube rupture (SGTR) and event-V PDSGs were not analyzed because of their containment bypass nature. After being benchmarked with the APETs, in terms of containment failure mode and risk, the SCETs were used to evaluate a number of potential containment modifications. The modifications were examined for their potential to mitigate or prevent containment failure from hydrogen burns or direct impingement on the containment by the core, (both factors identified as significant contributors to risk in the NUREG-1150 Sequoyah analysis). However, because of the relatively low baseline risk postulated for Sequoyah (i.e., 12 person-rems per reactor year), none of the potential modifications appear to be cost effective. 15 refs., 10 figs. , 17 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution; EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6286161
- Report Number(s):
- NUREG/CR-5602; EGG--2606; ON: TI91006041
- Country of Publication:
- United States
- Language:
- English
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ICE CONDENSERS
LOSS OF COOLANT
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MODIFICATIONS
P CODES
POWER REACTORS
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REACTOR ACCIDENTS
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SEQUOYAH-2 REACTOR
SOURCE TERMS
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210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
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ACCIDENTS
ATWS
BENCHMARKS
BLACKOUTS
COMPUTER CODES
CONDENSERS
CONTAINMENT
CONTAINMENT SYSTEMS
COST BENEFIT ANALYSIS
E CODES
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
ICE CONDENSERS
LOSS OF COOLANT
M CODES
MODIFICATIONS
P CODES
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
S CODES
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SOURCE TERMS
STEAM CONDENSERS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
TRANSIENTS
VAPOR CONDENSERS
WATER COOLED REACTORS
WATER MODERATED REACTORS