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Material Approved for Incorporation by Reference

(Revised as of January 1, 2001)

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

11 West 42nd Street, New York, NY 10036 Telephone: (212) 642– 4900

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

50.55a

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

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

III.A.3.a

Part 50, App. K,
I.A.4

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.

1968 Edition: Addenda Summer 68; Winter 68; Summer 69; Winter 50.55a 69; Summer 70; Winter 70.

10 CFR (PARTS 1-50)-Continued

NUCLEAR REGULATORY COMMISSION—Continued

1971 Edition: Addenda Summer 71; Winter 71; Summer 72; Winter 50.55a 72; Summer 73; Winter 73.

ASME Boiler and Pressure Vessel Code Section III, Division 1

1974 Edition: Addenda Summer 74; Winter 74; Summer 75; Winter 50.55a 75; Summer 76; Winter 76.

1977 Edition: Addenda Summer 77; Winter 77; Summer 78; Winter 50.55a 78; Summer 79; Winter 79.

1980 Edition: Addenda Summer 80;

50.55a

1981 Edition: Addenda Winter 1981

50.55a

1983 Edition: Addenda Summer 83; Winter 83; Summer 84; Winter 50.55a 84; Summer 85; Winter 85.

1986 Edition: 1986, 1987 and 1988 Addenda

50.55a

1989 Edition

50.55a

ASME Boiler and Pressure Vessel Code, Section III, Division 1, 1989
Addenda, 1990 Addenda, 1992 Edition, 1992 Addenda, 1993 Ad-
denda, 1994 Addenda, 1995 Edition, 1995 Addenda, 1996 Addenda.
ASME Boiler and Pressure Vessel Code Section III, 1980 Edition: 50.34
Subarticle CC-3720, Division 2.

50.55a

Subarticle NE-3220

50.34

ASME Boiler and Pressure Vessel Code Section XI, Division 1, 1970
Edition: Addenda Winter 70.

50.55a

1971 Edition: Addenda Summer 71; Winter 71; Summer 72; Winter 50.55a 72; Summer 73; Winter 73.

1974 Edition: Addenda Summer 74; Winter 74; Summer 75; Winter 50.55a 75; Summer 76; Winter 76.

1977 Edition: Addenda Summer 77; Winter 77; Summer 78; Winter 50.55a 78; Summer 79; Winter 79.

1980 Edition: Addenda Winter 80

50.55a

1981 Edition: Addenda Winter 81; Winter 82

50.55a

1983 Edition: Addenda Summer 83; Winter 83; Summer 84; Winter 50.55a 84; Summer 85; Winter 85.

1986 Edition: 1986, 1987 and 1988 Addenda

50.55a

1989 Edition

50.55a

ASME Boiler and Pressure Vessel Code, Section XI, Division 1, 1989 Addenda, 1991 Addenda, 1992 Edition, 1992 Addenda, 1993 Addenda, 1994 Addenda, 1995 Edition, 1996 Addenda.

50.55a

ASME Code for Operation and Maintenace of Nuclear Power Plants 50.55a
(OM Code) 1995 Edition, 1996 Addenda.

Draft ASME Code for Pumps and Valves for Nuclear Power, dated 50.55a
Nov. 1968 and 1 addenda dated Mar. 1970.

F. J. Moody, Maximum Flow Rate of a Single Component, Two-
Phase Mixture, Journal of Heat Transfer, Trans American Society
of Mechanical Engineers, 87, No. 1, Feb. 1965.

American Society for Testing Materials

100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, Telephone (610) 832-9585, FAX (610) 832-9555

Part 50, App. K,
I.C.1.b.

ASTM E 185-73, E 185-79 and E 185-82 Standard Recommended Part 50, App. H, I Practice for Surveillance Tests for Nuclear Reactor Vessels.

Commerce Department, National Technical Information Service
5285 Port Royal Rd., Springfield, VA 22161

Baker-Just, Studies of Metal Water Reactions at High Temperatures,
III. Experimental and Theoretical Studies of the Zirconium-Water
Reaction, ANL-6548, page 7, May 1962.

Part 50, App. K,

I.A.5

10 CFR (PARTS 1-50)—Continued

NUCLEAR REGULATORY COMMISSION Continued

PWR FLECHT (Full Length Emergency Cooling Heat Transfer) Final Part 50, App. K, Report, Westinghouse Report WCAP-7665, Apr. 1971.

General Electric Co.

Nuclear Energy Business Group, Technical Support Services, MC

211, 175 Curtner Ave., San Jose, CA 95125

I.D.5

Loss-of-Coolant Accident and Emergency Core Cooling Models for Part 50, App. K,

GE Boiling Water Reactors, GE Report NEDO-10329, Apr. 1971. Institute of Electrical and Electronic Engineers

Service Center, 445 Hoes Lane, P.O. Box 1331, Piscataway, NJ 08855-1331

I.D.7.c

IEEE-279 Criteria for Protection Systems for Nuclear Generating Sta- 50.55a(h)
tions, dated Aug. 30, 1968 and June 3, 1971.

IEEE Std. 603-1991, Standard Criteria for Safety Systems for Nuclear 50.55a(h)
Power Generating Stations, including correction sheet dated January
30, 1995.

IEEE 803-1983 Recommended Practices for Unique Identification in 50.73
Power Plants and Related Facilities-Principles and Definitions.

194-028 D-01--29

I

II

IV

I

Table of CFR Titles and Chapters

(Revised as of January 1, 2001)

Title 1-General Provisions

Administrative Committee of the Federal Register (Parts 1-49)
Office of the Federal Register (Parts 50-299)

Miscellaneous Agencies (Parts 400-500)

Title 2-[Reserved]

Title 3-The President

Executive Office of the President (Parts 100-199)

Title 4-Accounts

[blocks in formation]

V

VI

VII

VIII

IX

XI

XIV

The International Organizations Employees Loyalty Board (Parts 1500-1599)

Federal Retirement Thrift Investment Board (Parts 1600-1699) Advisory Commission on Intergovernmental Relations (Parts 1700-1799)

Office of Special Counsel (Parts 1800-1899)

Appalachian Regional Commission (Parts 1900-1999)

Armed Forces Retirement Home (Part 2100)

Federal Labor Relations Authority, General Counsel of the Federal Labor Relations Authority and Federal Service Impasses Panel (Parts 2400-2499)

Office of Administration, Executive Office of the President (Parts 2500-2599)

XV

XVI

Office of Government Ethics (Parts 2600-2699)

XXI

Department of the Treasury (Parts 3100-3199)

XXII ХХІІІ

Federal Deposit Insurance Corporation (Part 3201)
Department of Energy (Part 3301)

XXIV Federal Energy Regulatory Commission (Part 3401)

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