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power plant are not available after the occurrence of the Operating Basis Earthquake Ground Motion, the licensee must consult with the Commission and must propose a plan for the timely, safe shutdown of the nuclear power plant. Prior to resuming operations, the licensee must demonstrate to the Commission that no functional damage has occurred to those features necessary for continued operation without undue risk to the health and safety of the public and the licensing basis is maintained.

(4) Required Seismic Instrumentation. Suitable instrumentation must be provided so that the seismic response of nuclear power plant features important to safety can be evaluated promptly after an earthquake.

(b) Surface Deformation. The potential for surface deformation must be taken into account in the design of the nuclear power plant by providing reasonable assurance that in the event of deformation, certain structures, systems, and components will remain

functional. In addition to surface deformation induced loads, the design of safety features must take into account seismic loads and applicable concurrent functional and accident-induced loads. The design provisions for surface deformation must be based on its postulated occurrence in any direction and azimuth and under any part of the nuclear power plant, unless evidence indicates this assumption is not appropriate, and must take into account the estimated rate at which the surface deformation may occur.

(c) Seismically Induced Floods and Water Waves and Other Design Conditions. Seismically induced floods and water waves from either locally or distantly generated seismic activity and other design conditions determined pursuant to §100.23 of this chapter must be taken into account in the design of the nuclear power plant so as to prevent undue risk to the health and safety of the public.

[61 FR 65173, Dec. 11, 1996]

FINDING AIDS

A list of CFR titles, subtitles, chapters, subchapters and parts and an alphabetical list of agencies publishing in the CFR are included in the CFR Index and Finding Aids volume to the Code of Federal Regulations which is published separately and revised annually.

Material Approved for Incorporation by Reference

Table of CFR Titles and Chapters

Alphabetical List of Agencies Appearing in the CFR
List of CFR Sections Affected

Material Approved for Incorporation by Reference

(Revised as of January 1, 2002)

The Director of the Federal Register has approved under 5 U.S.C. 552(a) and 1 CFR Part 51 the incorporation by reference of the following publications. This list contains only those incorporations by reference effective as of the revision date of this volume. Incorporations by reference found within a regulation are effective upon the effective date of that regulation. For more information on incorporation by reference, see the preliminary pages of this volume.

10 CFR (PARTS 1-50)

NUCLEAR REGULATORY COMMISSION

Each of the following documents is available for inspection at the 10 CFR
Nuclear Regulatory Commission's Library, 11545 Rockville Pike,
Rockville, MD 20852-2738. The individual documents are available

through the sources listed below..

American Association of Physicists in Medicine

335 E. 45th St., New York, NY 10017

Scientific Committee on Radiation Dosimetry of the American Asso- 35.632(d) ciation of Physicists in Medicine, Physics in Medicine and Biology,

Volume 16, No. 3, 1971, 379–396.

Task Group 21 of the Radiation Therapy Committee, Medical Physics, 35.632(d)
Vol. 10, No. 6, 1983, pp. 741-771; and Volume 11, No. 2, 1984,
p. 213.

American National Standards Institute

25 West 43rd Street, Fourth floor, New York, NY 10036 Telephone: (212) 642-4900

ASA B31.1 1955 Ed., American Standard Code for Pressure Piping 50.55a USAS B31.1.0 1967 Ed., Addenda A, B & C, U.S.A. Standard Code 50.55a for Pressure Piping.

USAS B31.7 1969 Ed., Addenda A, B & C, U.S.A. Standard Code 50.55a for Pressure Piping.

ANSI N432-1980 Radiological Safety for the Design and Construction 34.20

of Apparatus for Gamma Radiography (published as NBS Handbook

136, issued January 1981).

ANSI N45.4-1972 Leakage Rate Testing of Containment Structures Part 50, App. J, for Nuclear Reactors, March 16, 1972.

American Nuclear Society

555 North Kensington Ave., La Grange Park, IL 60525

III.A.3.a

I.A.4

Proposed American Nuclear Society Standard-Decay Energy Release Part 50, App. K,
Rates Following Shutdown of Uranium Fueled Thermal Reactors,
Approved by Subcommittee ANS-5, ANS Standards Committee,
Oct. 1971.

American Society of Mechanical Engineers

Three Park Avenue, New York, New York 10016

ASME Boiler and Pressure Vessel Code Section III, 1963 Edition: 50.55a
Addenda Summer 64; Winter 64.

1965 Edition: Addenda Summer 65; Winter 65; Summer 66; Winter 50.55a
66; Summer 67; Winter 67.

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