Technical specification improvements to containment heat removal and emergency core cooling systems: Final report

Technical Report · Fri Jul 01 04:00:00 EDT 1988

OSTI ID:7175487

Sullivan, W P; Ha, C; Pentzien, D C; Visweswaran, S

This report presents the results of an analysis for technical specification improvements to the emergency core cooling systems (ECCS) and containment heat removal systems (EPRI Research Project 2142-3). The objective of this project is to further develop a reliability- and risk-based methodology to provide improvements by considering groups of surveillance test intervals and allowed out-of-service times jointly. This was done for the technical specifications for the ECCS, containment heat removal equipment, and supporting systems of a boiling water reactor plant. The project (1) developed a methodology for optimizing groups of surveillance test intervals and allowed out-of-service times jointly, (2) applied the methodology in a case study of a specific operating plant, Hatch-2, and (3) evaluated benefits of the application. The results of the case study demonstrate that beneficial technical specification improvements can be realized with application of the methodology. By tightening a small group of sensitive surveillance test intervals (STIs) and allowed out-of-service times (AOTs), a larger group of less sensitive STIs and AOTs can be extended resulting in an overall plant operating cost improvement without reducing the plant safety. The reliability- and risk-based methodology and results from this project can be effectively applied for technical specification improvements at other operating plants.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA); General Electric Co., San Jose, CA (USA). Nuclear Energy Business Operations
• OSTI ID: 7175487
• Report Number(s): EPRI-NP-5904; ON: TI88014204
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CODES
CONTAINMENT
COOLING SYSTEMS
DOCUMENT TYPES
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FLUID MECHANICS
HATCH-2 REACTOR
HEAT TRANSFER
HYDRAULICS
MECHANICS
POWER REACTORS
PROGRESS REPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
RISK ASSESSMENT
S CODES
SAFETY
SPECIFICATIONS
SURVEILLANCE
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS