Evaluation of safety implications of control systems in LWR nuclear power plants: Technical findings related to USI A-47: Final report
An in-depth evaluation was performed on non-safety-related control systems (see Section 1) that are typically used during normal plant operation on four nuclear steam supply system plants: a General Electric Company boiling-water reactor, a Westinghouse 3-loop pressurized-water reactor (PWR), a Babcock Wilcox Co. (B W) once-through steam generator PWR, and a Combustion Engineering PWR design. A study was also conducted to determine the generic applicability of the results to the class of plants represented by the specific plants analyzed. Generic conclusions were then developed. Steam generator and reactor vessel overfill events and reactor vessel overcooling events were identified as major classes of events having the potential to be more severe than previously analyzed. Specific substasks of this issue were to study these events to determine the need for preventive and/or mitigating design measures. This report describes the technical studies performed by the laboratories, the NRC staff assessment of the results, the generic applicability of the evaluations, and the technical findings resulting from these studies. This final report contains the staff's responses to, and resolution of, the public comments that were solicited and received before September 16,1988, in response to the draft reports issued for public comment on May 27, 1988. 39 refs, 1 fig., 7 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution
- OSTI ID:
- 6119114
- Report Number(s):
- NUREG-1217; ON: TI89014849
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTROL SYSTEMS
EVALUATION
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
STEAM GENERATORS
FAILURES
HYDRAULICS
LOSS OF COOLANT
PROBABILITY
PROGRESS REPORT
PUMPS
SHUTDOWNS
START-UP
ACCIDENTS
BOILERS
COOLING SYSTEMS
DOCUMENT TYPES
ENERGY SYSTEMS
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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210200 - Power Reactors
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