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FBO DAILY ISSUE OF MAY 06, 2012 FBO #3816
SOLICITATION NOTICE

A -- LEVEL 2 PRA LOGIC MODEL DEVELOPMENT AND THERMAL-HYDRAULIC MODELING AND ANALYSIS SUPPORT FOR THE FULL-SCOPE SITE LEVEL 3 PRA PROJECT

Notice Date
5/4/2012
 
Notice Type
Presolicitation
 
NAICS
541690 — Other Scientific and Technical Consulting Services
 
Contracting Office
Nuclear Regulatory Commission, Office of Administration, Division of Contracts, 12300 Twinbrook Parkway, Rockville, Maryland, 20852-2738, United States
 
ZIP Code
20852-2738
 
Solicitation Number
NRC-HQ-12-R-04-0099
 
Archive Date
7/3/2012
 
Point of Contact
Claudia G. Melgar, Phone: 301-492-3487, Jennifer A. Defino, Phone: 301-492-3637
 
E-Mail Address
Claudia.Melgar@nrc.gov, Jennifer.DeFino@nrc.gov
(Claudia.Melgar@nrc.gov, Jennifer.DeFino@nrc.gov)
 
Small Business Set-Aside
Total Small Business
 
Description
A full-scope site Level 3 probabilistic risk assessment (PRA) for a nuclear power plant site can provide valuable insights into the relative importance of various risk contributors by assessing accidents involving the reactor core as well as other site radiological sources (i.e., spent fuel pools, dry storage casks, and multiple units). These insights can be used to further enhance regulatory decision making and to help focus limited agency resources on issues most directly related to the agency's mission to protect public health and safety. Although Level 3 PRAs have since been performed to some extent within both the United States and international nuclear industries, the U.S. Nuclear Regulatory Commission (NRC) has not sponsored development of a Level 3 PRA for a nuclear power plant site since NUREG-1150. In the more than two decades that have passed since the NUREG-1150 Level 3 PRAs were performed, numerous technical advances have been made that were not reflected in the NUREG-1150 PRA models. The staff has also identified additional scope considerations not previously considered that could be addressed by performing a new full-scope site Level 3 PRA. A Level 2 PRA model provides 1) a structured and comprehensive evaluation of containment performance in response to accident sequences identified from the Level 1 analysis and 2) a quantitative characterization of radiological release to the environment that would result from accident sequences that involve leakage from the containment pressure boundary. Deterministic T-H modeling and analyses serve as the basis for many of the assumptions used in the Level 2 as well as the Level 1 PRA logic models. As such, the T-H models and analyses must adequately represent those systems and phenomena that are being modeled so that the PRA logic model represents realistic plant response to various accident scenarios.
 
Web Link
FBO.gov Permalink
(https://www.fbo.gov/spg/NRC/OA/DCPM/NRC-HQ-12-R-04-0099/listing.html)
 
Record
SN02739931-W 20120506/120504235624-b718ab37d63c0782d4fb2cfbd08a6735 (fbodaily.com)
 
Source
FedBizOpps Link to This Notice
(may not be valid after Archive Date)

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