DOE safety goals comparison using NUREG-1150 PRA (probabilistic risk assessment) methodology
A full-scope Level 3 probabilistic risk assessment (PRA) including external events has been performed for N Reactor, a US Department of Energy (DOE) Category A production reactor. This four-year, multi-million dollar task was a joint effort by Westinghouse Hanford Company, Science Applications International Corporation (SAIC), and Sandia National Laboratories (SNL). Technical lead in external events and NUREG-1150 methodology was provided by SNL. SAIC led the effort in the Level 1 analysis for the internally initiated events. Westinghouse Hanford supported the task in many key areas, such as data collection and interpretation, accident progression, system interaction, human factor analyses, expert elicitation, peers review, etc. The main objective of this Level 3 PRA are to assess the risks to the public and onsite workers posed by the operation of N Reactor, to identify modifications to the plant that could reduce the overall risk, and to compare those risks to the proposed DOE and Nuclear Regulatory Commission (NRC) quantitative safety goals. This paper presents the methodology adopted by Westinghouse Hanford and SNL for estimating individual health risks, and the comparison of the N Reactor results and DOE quantitative nuclear safety guidelines. This paper is devoted to DOE quantitative safety guidelines interpretation and comparison; the NRC safety objectives are also presented in order to compare N Reactor results to commercial nuclear power plants included in the NUREG-1150 study. 7 refs., 7 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6851795
- Report Number(s):
- WHC-SA-0822; CONF-900917--9; ON: DE90014401
- Country of Publication:
- United States
- Language:
- English
Similar Records
Probabilistic risk assessment of the N Reactor using NUREG-1150 methods
Probabilistic risk assessment of N Reactor using NUREG-1150 methods
Related Subjects
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
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
DISEASES
ENRICHED URANIUM REACTORS
FIRES
FISSION PRODUCT RELEASE
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
LWGR TYPE REACTORS
N-REACTOR
NATIONAL ORGANIZATIONS
NEOPLASMS
OCCUPATIONAL EXPOSURE
PERSONNEL
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PROBABILITY
PRODUCTION REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
STANDARDS
US DOE
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS