Organization for the performance of PRA programs. [PWR; BWR]
Conference
·
OSTI ID:6001386
A joint industry/NRC effort is currently underway to develop a procedures guide for performing probabilistic risk assessments (PRA) of nuclear power plants. Chapter 2 of the guide deals with the organization of the PRA. Four levels of scope for PRAs are defined. The methodology for performing the analysis is discussed in general, providing an overview of the tasks involved and the relationships among the various tasks. Management of the analysis, including means for helping to assure a quality analysis, is also discussed. Manpower and schedule estimates are provided for the information of organizations considering undertaking probabilistic risk assessments of varying scopes. The estimates reflect the performance of a PRA using the procedures contained in the guide.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Massachusetts Inst. of Tech., Cambridge (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6001386
- Report Number(s):
- SAND-81-1822C; CONF-810905-13; ON: DE81030682
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development and organization of the industry/NRC procedures guide
PRA Procedures Guide: a guide to the performance of probabilistic risk assessments for nuclear power plants. Final report, Volume 1 - Chapters 1-8. [PWR; BWR]
PRA procedures guide: a guide to the performance of probabilistic risk assessments for nuclear power plants. Review draft
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6076407
PRA Procedures Guide: a guide to the performance of probabilistic risk assessments for nuclear power plants. Final report, Volume 1 - Chapters 1-8. [PWR; BWR]
Technical Report
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5724111
PRA procedures guide: a guide to the performance of probabilistic risk assessments for nuclear power plants. Review draft
Technical Report
·
Mon Sep 28 00:00:00 EDT 1981
·
OSTI ID:5536481
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PLANNING
POWER PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PLANNING
POWER PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS