Southern California Edison instrument setpoint program
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7168370
- Southern California Edison Co., San Clemente (United States)
In November of 1989, the US Nuclear Regulatory Commission (NRC) conducted an electrical safety system functional inspection (ESSFI) at the San Onofre nuclear generating station (SONGS), which was followed by an NRC audit on instrument setpoint methodology in January 1991. Units 2 and 3 at SONGS are 1100-MW(electric) Combustion Engineering (C-E) pressurized water reactors (PWRs) operated by Southern California Edison (SCE). The purpose of this paper is to summarize the results of the NRC audit and SCE's follow-up activities. The NRC team inspection reinforced the need to address several areas relative to the SCE setpoint program. The calculations withstood the intensive examination of four NRC inspectors for 2 weeks and only a few minor editorial-type problems were noted. Not one of the calculated plant protections system setpoints will change as a result of the audit. There were no questions raised relative to setpoint methodology.
- OSTI ID:
- 7168370
- Report Number(s):
- CONF-911107--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ADMINISTRATIVE PROCEDURES
AUDITS
BOILERS
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DECISION MAKING
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ENGINEERED SAFETY SYSTEMS
ENGINEERING DRAWINGS
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ENRICHED URANIUM REACTORS
ERRORS
HEAT ENGINES
INTERNAL COMBUSTION ENGINES
LEVELS
NATIONAL ORGANIZATIONS
POWER REACTORS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
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SAN ONOFRE-2 REACTOR
SAN ONOFRE-3 REACTOR
SPECIFICATIONS
STEAM GENERATORS
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THERMAL REACTORS
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US ORGANIZATIONS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ADMINISTRATIVE PROCEDURES
AUDITS
BOILERS
CALIBRATION
DECISION MAKING
DESIGN
DIAGRAMS
DIESEL ENGINES
EDUCATION
ELECTRIC GENERATORS
ENGINEERED SAFETY SYSTEMS
ENGINEERING DRAWINGS
ENGINES
ENRICHED URANIUM REACTORS
ERRORS
HEAT ENGINES
INTERNAL COMBUSTION ENGINES
LEVELS
NATIONAL ORGANIZATIONS
POWER REACTORS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
REACTORS
SAN ONOFRE-2 REACTOR
SAN ONOFRE-3 REACTOR
SPECIFICATIONS
STEAM GENERATORS
TESTING
THERMAL REACTORS
TRAINING
US NRC
US ORGANIZATIONS
VALIDATION
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS