Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations
Creators
- 1. Science and Engineering Associates, Albuquerque, NM (United States)
Description
A Level III Probabilistic Risk Assessment (PRA) has been performed for LaSalle Unit 2 under the Risk Methods Integration and Evaluation Program (RMIEP) and the Phenomenology and Risk Uncertainty Evaluation Program (PRUEP). This report documents the phenomenological calculations and sources of. uncertainty in the calculations performed with HELCOR in support of the Level II portion of the PRA. These calculations are an integral part of the Level II analysis since they provide quantitative input to the Accident Progression Event Tree (APET) and Source Term Model (LASSOR). However, the uncertainty associated with the code results must be considered in the use of the results. The MELCOR calculations performed include four integrated calculations: (1) a high-pressure short-term station blackout, (2) a low-pressure short-term station blackout, (3) an intermediate-term station blackout, and (4) a long-term station blackout. Several sensitivity studies investigating the effect of variations in containment failure size and location, as well as hydrogen ignition concentration are also documented
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI93002331; NTIS; INIS; GPO.
Files
Additional details
Additional titles
- Subtitle (English)
- Volume 3
Publishing Information
- Imprint Pagination
- 571 p.
- Report number
- NUREG/CR--5305-Vol.3
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027174
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; CONTAINMENT SYSTEMS; FISSION PRODUCT RELEASE; HYDROGEN; IGNITION; LA SALLE COUNTY-2 REACTOR; M CODES; OUTAGES; REACTOR SAFETY; RISK ASSESSMENT; SOURCE TERMS
- Descriptors DEC
- BWR TYPE REACTORS; COMPUTER CODES; CONTAINMENT; ELEMENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- SAND--90-2765-Vol.3.