Published April 1975
| Version v1
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Basis for heatup and cooldown limit curves
Description
A description is presented on how the provisions of Appendix G to Section III of the ASME Code (Summer 1972 Addenda) are used by Westinghouse Electric Corporation's Nuclear Energy Systems Division to develop the pressure-temperature limits for normal operation and core operation that is included in the Technical Specifications. The methods used to conservatively estimate the required material properties in those cases where material was procured and tested prior to the application of the expanded test requirements are also described. (U.S.)
Availability note (English)
MF available from INIS under the Report Number.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 49 p.
- Report number
- WCAP--7924-A
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7225516
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- MECHANICAL PROPERTIES; PWR TYPE REACTORS; REACTOR MATERIALS; REACTOR OPERATION; SPECIFICATIONS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- OPERATION; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Westinghouse Electric Corp., Pittsburgh.