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Title: Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations. Volume 3

Abstract

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.

Authors:
 [1]; ;
  1. Science and Engineering Associates, Albuquerque, NM (United States)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
10191298
Report Number(s):
NUREG/CR-5305-Vol.3; SAND-90-2765-Vol.3
ON: TI93002331
DOE Contract Number:  
AC04-76DP00789
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Oct 1992
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LA SALLE COUNTY-2 REACTOR; RISK ASSESSMENT; COMPUTER CALCULATIONS; M CODES; BLACKOUTS; CONTAINMENT SYSTEMS; HYDROGEN; IGNITION; FISSION PRODUCT RELEASE; SOURCE TERMS; REACTOR SAFETY; 220900; 210100; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED

Citation Formats

Shaffer, C J, Miller, L A, and Payne, Jr, A C. Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations. Volume 3. United States: N. p., 1992. Web.
Shaffer, C J, Miller, L A, & Payne, Jr, A C. Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations. Volume 3. United States.
Shaffer, C J, Miller, L A, and Payne, Jr, A C. 1992. "Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations. Volume 3". United States.
@article{osti_10191298,
title = {Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations. Volume 3},
author = {Shaffer, C J and Miller, L A and Payne, Jr, A C},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/10191298}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Oct 01 00:00:00 EDT 1992},
month = {Thu Oct 01 00:00:00 EDT 1992}
}

Technical Report:
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