The NUREG-1150 probabilistic risk assessment for the Surry nuclear power station
Creators
- 1. Sandia National Labs., Albuquerque, NM (United States)
- 2. Arizona State Univ., Tempe, AZ (United States)
- 3. Technadyne, Inc. (United States)
- 4. Science Applications International Corp. (United States)
- 5. Applied Physics, Inc. (United States)
Description
This paper summarizes the findings of the probabilistic risk assessment for Unit 1 of the Surry Power Station performed in support of NUREG-1150. The emphasis is on the 'back-end' analyses, that is, the accident progression, source term, and consequence analyses, and the risk results obtained when the results of these analyses are combined with the accident frequency analysis. The results show that the risk from internal initiators is well below the safety goals and is somewhat lower than estimated by Reactor Safety Study (RSS) over a decade ago. The risk from internal initiators is dominated by bypass accidents in the current analysis. The risk from seismic initiators is comparable to or greater than the risk from internal initiators, but still less than that estimated for internal initiators in the RSS. The uncertainty band for both types of initiators is considerably greater than that estimated in RSS. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 135
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 29-59
- ISSN
- 0029-5493
- CODEN
- NEDEA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 23075943
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT; FAILURES; FISSION PRODUCT RELEASE; FREQUENCY ANALYSIS; LOSS OF COOLANT; NEOPLASMS; PROBABILISTIC ESTIMATION; PROBABILITY; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; SURRY-1 REACTOR; SURRY-2 REACTOR
- Descriptors DEC
- ACCIDENTS; DISEASES; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC04-76DP00789