Published October 1978
| Version v1
Report
Restricted
Mark II containment lead plant program load evaluation and acceptance criteria
Description
The report, prepared by the Office of Nuclear Reactor Regulation, addresses the portion of the Mark II owner's program that provides a generic methodology for establishing design basis LOCA and safety relief valve loads for the lead Mark II facilities (Zimmer, Shoreham, and LaSalle), i.e., the lead plant program. The report includes an evaluation of the Mark II owner's load methodology, a description of load methodologies that we find acceptable for use in the individual plant unique assessments, and the basis for the stated conclusions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A15/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- BWR
Publishing Information
- Imprint Pagination
- 327 p.
- Report number
- NUREG--0487
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10448880
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; LOSS OF COOLANT; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS