HTGR edition of the standard format and content of safety analysis reports for nuclear power plants Page: 76 of 233
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(2) the applicable codes, standards, specifications, regulations, 0
safety guides and industry standard practices,
(3) the loading criteria, including the loading and load combinations,
(4) the computational techniques and analytical procedures,
(5) the structural design acceptance criteria such as stress
allowables, strain allowables, deformation limits, strength
capabilities and other behavior or response criteria and the
design comparisons to these criteria,
(6) the material, quality control measures and construction
techniques, and
(7) the testing and surveillance requirements.
The following information should be provided.
3.8.1.1 Description of the Containment - A physical description of
the containment should be provided, and supplemented with sketches or
diagrams as necessary. Unique or new features of the containment should
be identified. The descriptions should be sufficient to provide the
complete geometry of the structure.
The tendon system including the embedded sheaths should be described.
The arrangement of the prestressing tendons or the reinforcing steel,
especially at penetrations, splices, anchorage zones, connections, joints
and other discontinuities should be provided.
3.8.1.2 Applicable Codes, Standards, and Specifications - The design
codes, standards, specifications, regulations, general design criteria,
safety guides and other industry standard practices that are applied
should be identified with respect to the containment. The specific
edition, date, or addenda of the applicable documents should be identified
including any exceptions taken, and their justification, and/or applica-
tion of substitute provisions. The limitations and assumptions made in
the referenced documents should be discussed in relation to the procedures
outlined for the design of the facility. A summary of plant principal
specifications as prepared by the structural designer should be furnished.
Applicable AEC Safety Guides should be listed. In addition, it should be
indicated which of the safety guides the applicant chose to comply with.
The provisions of ACI 318-71 including Chapters 18 and 19 as well as
Appendix A that are utilized should be identified. Portions of documents
or entire documents such as the ACI 349 Committee Report, "Criteria for
Reinforced Concrete Nuclear Power Containment Structures," and/or the3.8-2
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HTGR edition of the standard format and content of safety analysis reports for nuclear power plants, report, July 1, 1973; United States. (https://digital.library.unt.edu/ark:/67531/metadc1017707/m1/76/: accessed April 23, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.