Interim reliability-evaluation program: analysis of the Millstone Point Unit 1 nuclear power plant. Volume IV. Appendix B. 9 through B. 19 and C

Technical Report · Sun May 01 00:00:00 EDT 1983

DOI:https://doi.org/10.2172/5932669· OSTI ID:5932669

Curry, J J; Gallagher, D W; Modarres, M; Radder, J A

Appendices are presented concerning isolation condenser makeup; vapor suppression system; station air system; reactor building closed cooling water system; turbine building secondary closed water system; service water system; emergency service water system; fire protection system; emergency ac power; dc power system; event probability estimation; methodology of accident sequence quantification; and assignment of dominant sequences to release categories.

• Research Organization: Science Applications, Inc., Bethesda, MD (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5932669
• Report Number(s): NUREG/CR-3085/4; SAND-82-7212/4; ON: DE83015750
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MILLSTONE-1 REACTOR
AUXILIARY WATER SYSTEMS
ENGINEERED SAFETY SYSTEMS
POWER SUPPLIES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
ACCIDENTS
AUXILIARY SYSTEMS
BWR TYPE REACTORS
ELECTRONIC EQUIPMENT
ENRICHED URANIUM REACTORS
EQUIPMENT
POWER REACTORS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled