Shutdown decay heat removal analysis: Plant case studies and special issues: Summary report

Technical Report · Sat Apr 01 04:00:00 EST 1989

OSTI ID:6149494

Ericson, Jr, D M; Cramond, W R; Sanders, G A; Hatch, S W

Shutdown Decay Heat Removal Requirements has been designated as Unresolved Safety Issue (USI) A-45. The overall objectives of the USI A-45 program were to evaluate the safety adequacy of decay heat removal (DHR) systems in existing light water reactor nuclear power plants and to assess the value and impact (benefit-cost) of alternative measures for improving the overall reliability of the DHR function. To provide the technical data required to meet these objectives a program was developed that examined the state of DHR system reliability in a sample of existing plants. This program identified potential vulnerabilities and identified and established the feasibility of potential measures to improve the reliability of the DHR function. A value/impact (V/I) analysis of the more promising of such measures was conducted and documented. This report summarizes those studies. In addition, because of the evolving nature of V/I analyses in support of regulation, a number of supporting studies related to appropriate procedures and measures for the V/I analyses were also conducted. These studies are also summarized herein. This report only summarizes findings of technical studies performed by Sandia National Laboratories as part of the program to resolve this issue. 46 refs., 7 figs., 124 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution; Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6149494
• Report Number(s): NUREG/CR-5230; SAND-88-2375; ON: TI89011656
• 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
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BWR TYPE REACTORS
COOLING SYSTEMS
COST BENEFIT ANALYSIS
DOCUMENT TYPES
ENERGY SYSTEMS
ENERGY TRANSFER
FEASIBILITY STUDIES
FLUID MECHANICS
HEAT TRANSFER
HISTORICAL ASPECTS
HYDRAULICS
MECHANICS
NATIONAL ORGANIZATIONS
PROBABILISTIC ESTIMATION
PROGRESS REPORT
PWR TYPE REACTORS
RADIATION PROTECTION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RECOMMENDATIONS
REMOVAL
RISK ASSESSMENT
SAFETY
SHUTDOWNS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS