Analysis of core damage frequency: Zion, Unit 1 internal events
Technical Report
·
OSTI ID:7126377
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
This document contains the accident sequence analyses of internally initiated events for the Zion Unit 1 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of the work published in October 1986 as NUREG/CR-4550 Volume 7. It addresses comments from numerous reviewers and provides significantly more detailed modeling of most aspects of the Zion plant. The mean core damage frequency at Zion was calculated to be 3.4E-4 per year, with a 95% upper bound of 8.4E-4 per year and a 5% lower bound of 1.1E-4 per year. Note that this range is based only on the statistical treatment of six specific issues. Reactor coolant pump seal loss of coolant accidents (LOCAs) were the largest contributors to the core damage frequency, accounting for approximately 85% of the total. 8 refs., 37 figs., 169 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 7126377
- Report Number(s):
- NUREG/CR-4550-Vol.7-Rev.1; EGG--2554-Vol.7-Rev.1; ON: TI90012647
- Country of Publication:
- United States
- Language:
- English
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DAMAGE
DATA
DATA BASE MANAGEMENT
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FLUID MECHANICS
FREQUENCY ANALYSIS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MANAGEMENT
MECHANICS
NUMERICAL DATA
POWER REACTORS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
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REACTOR SAFETY
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RISK ASSESSMENT
SAFETY
SEALS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR