U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 2-13
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Throughout the course of the review of a nuclear facility as part of
the procedure leading to a construction permit or an operating license,
copies of all pertinent documents submitted by the applicant or prepared
by the AEC are filed in the Public Document Room, 1717 H Street, Washington
25, D. C., where they may be examined.
A guide to the purpose, organization, and contents of safety analy-
sis reports has been prepared by DRL. 12 The material that follows is in-
tended to be a guide to codes, criteria, and regulations as applied to
containment and should not be construed as an interpretation of Commission
regulations or the specific process of evaluating the safety of a given
2.3.2 Code of Federal Regulations
All federal regulations pertaining to atomic energy are published in
Atomic Energy Rules and Regulations, Title 10, Code of Federal Regula-
tions.13 The Code is a loose-leaf document because continual revisions
are necessary to keep pace with an inherently dynamic situation. The
following parts are pertinent to the subject of codes, criteria, and regu-
1. Part 20 Standards for Protection Against Radiation
2. Part 50 Licensing of Production and Utilization Facilities
3. Part 100 Reactor Site Criteria
4. Part 115 Procedures for Review of Certain Nuclear Reactors Ex-
empted from Licensing Requirements
The Commission regulations are, in effect, summarized in the subse-
quent sections of this chapter. Proposed regulations are published in the
Federal Register for comments, and the comments are reviewed. When deemed
advisable, they are incorporated into the final version of the regulation,
which is then placed in effect by decree.
2.3.3 Construction Permit
As discussed in Part 50 of the Code, "Licensing of Production and
Utilization Facilities, a permit must be issued by the AEC before con-
struction of a utilization facility" may commence. "Utilization facility
is defined in the Code, Sect. 50.2(b), as any nuclear reactor other than
one designed or used primarily for the production of plutonium, in which
event the reactor would be a production facility under Sect. llt of the Act
and Sect. 50.2(a) of the Code. Reactors are licensed under Sect. 103, 104,
and 185 of the Act. The permit or license is explicit in setting out the
conditions under which the facility may be constructed and operated. The
permit or license also usually contains the authority to receive and use
special nuclear material in certain amounts, source material as required
by the type of facility, and certain by-product material that may be pro-
duced incidentally by operation of the facility. The term "construction"
does not include site exploration, site excavation, preparation of the site
for construction of the facility, or construction of roadways, railroad
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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/m1/99/: accessed March 25, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.