Published February 1985
| Version v1
Report
Utility perspective on PRA applications
Description
Northeast Utilities has established probabilistic risk assessment (PRA) capabilities sufficient to perform, use, and maintain PRA models for each of its operating nuclear units. The use of PRAs has proven valuable in safety management and as a decision tool in engineering and operational areas. The use of PRA models is being integrated into the design and operational programs currently in place at NU. PRA's either completed or in progress at Millstone-1, Millstone-3, and Connecticut Yankee power plants are briefly discussed
Additional details
Publishing Information
- Imprint Title
- International topical meeting on probabilistic safety methods and applications: proceedings. Volume 2. Sessions 9-16
- Journal Page Range
- p. 73.1-73.10.
- Report number
- EPRI-NP--3912-SR-Vol.2
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24 Feb - 1 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023521
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONNECTICUT YANKEE REACTOR; FAULT TREE ANALYSIS; MILLSTONE-1 REACTOR; MILLSTONE-3 REACTOR; MONTE CARLO METHOD; PROBABILITY; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; RISK ASSESSMENT; SPECIFICATIONS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS