U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 2-06
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The Board is separated from the staff and the Commission and does not com-
municate with counsel, members of the staff, or parties to a proceeding,
except upon the record or as otherwise permitted by law.
2.2.2 Advisory Committee on Reactor Safeguards
The Advisory Committee on Reactor Safeguards (ACRS) was established
to review the design (including containment provisions) of all proposed
power reactors. An advisory service was initially intended, but the
Atomic Energy Act of 1954 was amended4 in Section 29 on September 2, 1957
to give ACRS statutory status and to make hearings mandatory on specified
facility licenses. The ACRS has an authorized membership of 15, and each
member is a recognized expert in some phase of nuclear reactor technology.
These men are appointed to four-year terms by the AEC.
The 1957 amendment to the Atomic Energy Act authorized the Commis-
sion to request advice from the ACRS on any reactor safety problem and
directed the Commission to obtain such counsel on all power and test re-
actors considered for licensing by the Commission. Subsequently, by issu-
ance of Part 115, Title 10, Code of Federal Regulations,5 the Commission
was also required to obtain these services for other nuclear reactors,
e.g., Commission-owned reactors which would otherwise be exempted from
licensing requirements. The procedures for the review of such facilities
are known as parallel procedures, since the procedures parallel those
for licensed facilities, even though such a license is not required for
ACRS concern regarding some aspects of containment and related safety
features was indicated by recommendations made to Chairman Seaborg of the
AEC on September 11, 1961. Some of these recommendations were that6
"(1) Except in special units, all nuclear vessels and
piping be designed, built, and inspected in accordance with
one of the recognized codes and that no deviation be permitted
except as provided by the code used;
"(2) In selection of vendors for supplying equipment
for use in nuclear installations, recognition be given to the
need for care beyond code requirements in selection of materials,
control of fabrication, and testing;
1(3) In the Hazards Summary Report, (a) the code used
be specified, and (b) assurance be given that adequate con-
comitant material selection, manufacturing procedure, and
testing will be used; ...."
As noted earlier the containment system is but one of several engi-
neered safeguards that have been used or considered for use with nuclear
facilities. The ACRS also expressed itself in a letter of April 18, 1963,
to AEC Chairman Seaborg regarding the testing requirements for engineered
The increasing pressure to locate nuclear power plants
near population centers requires that designers of these
plants incorporate in their designs engineered safeguards
to reduce the magnitude of postulated radioactivity releases.
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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/m1/92/: accessed March 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.