Effects of control system failures on transients and accidents at a 3-loop Westinghouse pressurized water reactor. Volume 2. Appendices
Description
Safety Implications of Control Systems (A-47) was approved as an Unresolved Safety Issue (USI) by the Nuclear Regulatory Commission (NRC) in December of 1980. USI A-47 is concerned with the potential for transients or accidents being made more severe than previously analyzed as a result of control system failures. This report describes the work performed on the effects of control system failures on transients and accidents at a Westinghouse 3-loop pressurized water reactor. In this volume, the appendices contain detailed information consisting of the FMEA (failure mode and analysis) results, an in-depth description of the computer model, the deterministic computer analyses, and responses to comments made by Carolina Power and Light Company and Westinghouse Electric Corporation
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A11/MF A01 - GPO as TI86002826.
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Additional details
Publishing Information
- Imprint Pagination
- 231 p.
- Report number
- NUREG/CR--4326-Vol.2
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17028455
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAILURES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; ROBINSON-2 REACTOR; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EGG--2405-Vol.2.