Anticipated transients without scram program: common mode failure analysis of control rod drive mechanism
As part of the Anticipated Transient Without Scram (ATWS) program, Diamond Power Specialty Corporation's control rod drive mechanism (CRDM) was evaluated to determine its susceptibility to common mode failure. This study qualitatively evaluates the credibility of mechanical failure of a significant number of control rods to insert into the reactor core by trip on loss of power to the CRDM stators or to achieve powered insertion if power is available to the stators. The analytical procedure is a modification of the ''Extended Qualitative Analysis,'' Section 4.5 of IEEE Std 352-1972, 1974 Revision, ''General Principles for Reliability Analysis of Nuclear Power Generating Station Protection Systems. It is concluded that a simultaneous mechanical common mode failure of the trip function in all CRDM's is incredible; furthermore, there is no credible mechanical common mode failure of both trip and powered insertion capability in all CRDMs. (auth)
- Research Organization:
- Babcock and Wilcox Co., Lynchburg, Va. (USA). Nuclear Power Generation Div.
- NSA Number:
- NSA-33-002421
- OSTI ID:
- 4156736
- Report Number(s):
- BAW-10101
- Resource Relation:
- Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N77200 -Reactors-Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
220900* -Nuclear Reactor Technology-Reactor Safety
*CONTROL ROD DRIVES- FAILURES
*PWR TYPE REACTORS- ATWS
PROBABILITY
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY