Improvements to the original NUREG-1150 accident sequence analyses
Conference
·
OSTI ID:5911307
Since the accident sequence analyses to support the draft NUREG-1150 were published (NUREG/CR-4550), comments have been received from the utilities, the Nuclear Regulatory Commission, the nuclear industry, and the public. It is the intent to incorporate comments to the extent possible, along with anticipated changes produced by the analysis teams. The purpose of this paper is to identify the important comments and issues that will be addressed for each plant during the reanalysis. There are a few general changes in the methodology that apply to all of the plants. The most important change is an improved uncertainty analysis, including a more comprehensive treatment of uncertainty issues and a more defensible approach to eliciting expert opinion on these issues. Another important change is the addition of external events to the analysis of the Surry and Peach Bottom plants. These and other changes are discussed in this paper. 8 refs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5911307
- Report Number(s):
- SAND-87-1898C; CONF-8710111-1; ON: DE88001653
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5746390
Characterization of the internal event frequencies for the final NUREG-1150
Conference
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OSTI ID:5074307
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Conference
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Thu Dec 31 23:00:00 EST 1987
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:5655317
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
BWR TYPE REACTORS
DATA BASE MANAGEMENT
DISASTERS
ENRICHED URANIUM REACTORS
FAILURES
FAULT TREE ANALYSIS
FIRES
FLOODS
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
MANAGEMENT
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SEISMIC EFFECTS
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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
BWR TYPE REACTORS
DATA BASE MANAGEMENT
DISASTERS
ENRICHED URANIUM REACTORS
FAILURES
FAULT TREE ANALYSIS
FIRES
FLOODS
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
MANAGEMENT
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SEISMIC EFFECTS
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS