10 CFR (PARTS 1 - 50)
NUCLEAR REGULATORY COMMISSION |
Each of the following documents is available for inspection at the Nuclear Regulatory Commission's Library, 11545 Rockville Pike, Rockville, MD 20852-2738. The individual documents are available through the sources listed below. |
10 CFR |
American Association of Physicists in Medicine
335 E. 45th St., New York, NY 10017 |
Scientific Committee on Radiation Dosimetry of the American Association of Physicists in Medicine, Physics in Medicine and Biology, Volume 16, No. 3, 1971, 379-396. |
35.632(d) |
Task Group 21 of the Radiation Therapy Committee, Medical Physics, Vol. 10, No. 6, 1983, pp. 741-771; and Volume 11, No. 2, 1984, p. 213. |
35.632(d) |
|
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 for Pressure Piping. |
50.55a |
USAS B31.7 1969 Ed., Addenda A, B & C, U.S.A. Standard Code for Pressure Piping. |
50.55a |
ANSI N432-1980 Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography (published as NBS Handbook 136, issued January 1981). |
34.20 |
ANSI N45.4-1972 Leakage Rate Testing of Containment Structures for Nuclear Reactors, March 16, 1972. |
Part 50, App. J, III.A.3.a |
|
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. |
Part 50, App. K, I.A.4 |
|
American Society of Mechanical Engineers
Three Park Avenue, New York, New York 10016 |
ASME Boiler and Pressure Vessel Code Section III 1963 Edition: Addenda Summer 64; Winter 64. |
50.55a |
1965 Edition: Addenda Summer 65; Winter 65; Summer 66; Winter 66; Summer 67; Winter 67. |
50.55a |
1968 Edition: Addenda Summer 68; Winter 68; Summer 69; Winter 69; Summer 70; Winter 70. |
50.55a |
1971 Edition: Addenda Summer 71; Winter 71; Summer 72; Winter 72; Summer 73; Winter 73. |
50.55a |
ASME Boiler and Pressure Vessel Code Section III, Division 1, 1974 Edition: Addenda Summer 74; Winter 74; Summer 75; Winter 75; Summer 76; Winter 76. |
50.55a |
1977 Edition: Addenda Summer 77; Winter 77; Summer 78; Winter 78; Summer 79; Winter 79. |
50.55a |
1980 Edition: Addenda Summer 80 |
50.55a |
1981 Edition: Addenda Winter 1981 |
50.55a |
1983 Edition: Addenda Summer 83; Winter 83; Summer 84; Winter 84; Summer 85; Winter 85. |
50.55a |
1986 Edition: 1986, 1987, 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 Addenda, 1994 Addenda, 1995 Edition, 1995 Addenda, 1996 Addenda. |
50.55a |
ASME Boiler and Pressure Vessel Code, Section III, Division 1, 1997 Addenda, 1998 Edition, 1999 Addenda and 2000 Addenda. |
50.55a |
ASME Boiler and Pressure Vessel Code, Section III, Division 1, 2001 Edition, 2002 and 2003 Addenda. |
50.55a |
ASME Boiler and Pressure Vessel Code Section III, 1980 Edition: Subarticle CC-3720, Division 2. |
50.34 |
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 72; Summer 73; Winter 73. |
50.55a |
1974 Edition: Addenda Summer 74; Winter 74; Summer 75; Winter 75; Summer 76; Winter 76. |
50.55a |
1977 Edition: Addenda Summer 77; Winter 77; Summer 78; Winter 78; Summer 79; Winter 79. |
50.55a |
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 84; Summer 85; Winter 85. |
50.55a |
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 Boiler and Pressure Vessel Code, Section XI, Division 1, 1997 Addenda, 1998 Edition, 1999 Addenda. and 2000 Addenda. |
50.55a |
ASME Boiler and Pressure Vessel Code, Section XI, Division 1, 2001 Edition, 2002 and 2003 Addenda. |
50.55a |
ASME Code for Operation and Maintenance of Nuclear Power Plants (OM code) 1995 Edition, 1996 Addenda |
50.55a |
ASME Code for Operation and Maintenance of Nuclear Power Plants (OM code) 1997 Addenda, 1998 Edition, 1999 Addenda and 2000 Addenda. |
50.55a |
ASME Code for Operation and Maintenance of Nuclear Power Plants (OM code) 2002 and 2003 Addenda. |
50.55a |
Draft ASME Code for Pumps and Valves for Nuclear Power, dated Nov. 1968 and 1 addenda dated Mar. 1970. |
50.55a |
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. |
Part 50, App. K, I.C.1.b. |
|
American Society for Testing Materials
100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, Telephone (610) 832-9585, FAX (610) 832-9555 |
ASTM E 185-73, E 185-79 and E 185-82 Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels. |
Part 50, App. H, I |
|
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 |
PWR FLECHT (Full Length Emergency Cooling Heat Transfer) Final Report, Westinghouse Report WCAP-7665, Apr. 1971. |
Part 50, App. K, I.D.5 |
|
General Electric Co.
Nuclear Energy Business Group, Technical Support Services, MC-211, 175 Curtner Ave., San Jose, CA 95125 |
Loss-of-Coolant Accident and Emergency Core Cooling Models for GE Boiling Water Reactors, GE Report NEDO-10329, Apr. 1971. |
Part 50, App. K, I.D.7.c |
|
Institute of Electrical and Electronic Engineers
IEEE Service Center, 445 Hoes Lane, P.O. Box 1331, Piscataway, NJ 08855-1331 |
IEEE-279 Criteria for Protection Systems for Nuclear Generating Stations, dated Aug. 30, 1968 and June 3, 1971. |
50.55a(h) |
IEEE Std. 603-1991, Standard Criteria for Safety Systems for Nuclear Power Generating Stations, including correction sheet dated January 30, 1995. |
50.55a(h) |
IEEE 803-1983 Recommended Practices for Unique Identification in Power Plants and Related Facilities--Principles and Definitions. |
50.73 |
|
National Fire Protection Association (NFPA)
NFPA Customer Service Department, 1 Batterymarch Park, P.O. Box 9101, Quincy, MA 02269-9101 |
NFPA Standard 805: Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. |
50.48 |
|
U.S. Nuclear Regulatory Commission
NRC Library, Two White Flint North, 11545 Rockville Pike, Rockville, MD 20852-2738 |
NRC Regulatory Guide 1.147 (Revision 0): Inservice Inspection Code Case Acceptability ASME Section XI Division 1, including Revisions 1 through 14 (Date of original issue: February 1981; Date of Revision 14: August 2005). |
50.55a(b) |
NRC Regulatory Guide 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 33, dated August 2005. |
50.55a(b) |
NRC Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, dated June 2003. |
50.55a(b) |