U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 2-14
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spurs, and transmission lines. In addition, the term "construction" does
not include construction of nonnuclear facilities (such as turbine-
generators and turbine buildings) and temporary buildings, such as con-
struction equipment storage sheds.
There are several steps involved in the issuance of a construction
permit; in the typical case they would include the following:
1. application for a construction permit, submittal of a prelimi-
nary safety analysis report (also called a site evaluation re-
port because of the function which it is intended to serve),
2. review of case by Commission staff (DRL),
3. review of case by Advisory Committee on Reactor Safeguards,
4. public hearing before an Atomic Safety and Licensing Board ap-
pointed by the Commission,
5. granting or denial of the construction permit.
The above list is not intended to imply that the review procedures
follow in the sequence indicated without any intermediate steps. Follow-
ing steps 2 or 3 or both the applicant is frequently asked to supply ad-
ditional information to supplement that in the preliminary safety analysis
report. The application is then evaluated in light of this additional
information, which usually becomes a part of the license application.
The request for a construction permit is made to the Commission
early in the history of the project. As the name implies, it is a request
for authorization to begin fabrication and erection of the reactor complex.
A preliminary safety analysis report is submitted with the request. Its
purpose is to provide sufficient information to permit an evaluation of
the potential hazards that might be encountered during normal operation,
as well as the consequences of these accidents, including the maximum
credible accident (mca). It should contain as much meaningful information
concerning the installation and safety status as is practical to develop,
considering the conceptual state of the design. Some areas of major im-
portance that should be covered in the report include descriptions of the
1. reactor site,
2. containment system,
4. primary coolant system,
5. power conversion system,
6. instrumentation and control systems,
7. accidents, potential hazards, maximum credible accident, and de-
tailed consideration of proposed safeguards.
At the construction permit stage all design details and reactor be-
havior may not be firmly established. The applicant is thus expected to
indicate some upper boundary for the hazards so that subsequent systematic
analyses will (in all probability) show credible accidents to be below the
prescribed upper boundary.
The application for a construction permit, accompanied by a prelimi-
nary safety analysis report, is submitted to the local AEC Operations Of-
fice as the first formal step in the licensing process. The application
and report, with AEC Operations Office review comments and recommendations,
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Cottrell, William B. & Savolainen, A. W. U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1, report, August 1965; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc101033/m1/100/: accessed March 20, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.