Evaluation of severe accident risks: Surry Unit 1
Technical Report
·
OSTI ID:6492238
- Sandia National Labs., Albuquerque, NM (USA)
- Arizona State Univ., Tempe, AZ (USA)
- Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA)
- Science Applications International Corp., Albuquerque, NM (USA)
In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported in NUREG-1150, the Severe Accident Risk Reduction Program (SARRP) has completed a revised calculation of the risk to the general public from severe accidents at the Surry Power Station, Unit 1. This power plant, located in southeastern Virginia, is operated by the Virginia Electric Power Corp. The emphasis in this risk analysis was not on determining a so-called'' point estimate of risk. Rather, it was to determine the distribution of risk, and to discover the uncertainties that account for the breadth of this distribution. Off-site risk initiation by events, both internal to the power station and external to the power station were assessed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6492238
- Report Number(s):
- NUREG/CR-4551-Vol.3-Rev.1-Pt.1; SAND--86-1309-Vol.3-Rev.1-Pt.1; ON: TI91004091; CNN: A1322
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of severe accident risks: Surry Unit 1
Evaluation of severe accident risks, Peach Bottom, Unit 2: Main report
Evaluation of Severe Accident Risks: Grand Gulf, Unit 1: Main Report (Vol.6, Rev.1)
Technical Report
·
Mon Oct 01 00:00:00 EDT 1990
·
OSTI ID:6491785
Evaluation of severe accident risks, Peach Bottom, Unit 2: Main report
Technical Report
·
Fri Nov 30 23:00:00 EST 1990
·
OSTI ID:6188992
Evaluation of Severe Accident Risks: Grand Gulf, Unit 1: Main Report (Vol.6, Rev.1)
Technical Report
·
Fri Nov 30 23:00:00 EST 1990
·
OSTI ID:6120530
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
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
CONTAINMENT
DATA
DOSES
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
HAZARDS
HEALTH HAZARDS
INFORMATION
M CODES
NUMERICAL DATA
P CODES
POWER REACTORS
PWR TYPE REACTORS
RADIATION DOSES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
S CODES
SAFETY
SEISMIC EFFECTS
SENSITIVITY ANALYSIS
SOURCE TERMS
STATISTICAL DATA
SURRY-1 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
CONTAINMENT
DATA
DOSES
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
HAZARDS
HEALTH HAZARDS
INFORMATION
M CODES
NUMERICAL DATA
P CODES
POWER REACTORS
PWR TYPE REACTORS
RADIATION DOSES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
S CODES
SAFETY
SEISMIC EFFECTS
SENSITIVITY ANALYSIS
SOURCE TERMS
STATISTICAL DATA
SURRY-1 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS