Source: https://gov.ecfr.io/cgi-bin/text-idx?mc=true&tpl=ibr/10V1.tpl
Timestamp: 2019-12-12 01:02:33
Document Index: 176416021

Matched Legal Cases: ['ARTS 1', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50']

10 CFR (PARTS 1–50)
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
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 for Pressure Piping
USAS B31.7 1969 Ed., Addenda A, B & C, U.S.A. Standard Code for Pressure Piping
ANSI N432–1980 Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography (published as NBS Handbook 136, issued January 1981)
ANSI N45.4–1972 Leakage Rate Testing of Containment Structures for Nuclear Reactors, March 16, 1972
Part 50, App. J, III.A.3.a
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
ASME Boiler and Pressure Vessel Code Section III, 1963 Edition: Addenda Summer 64; Winter 64
1965 Edition: Addenda Summer 65; Winter 65; Summer 66; Winter 66; Summer 67; Winter 67
1968 Edition: Addenda Summer 68; Winter 68; Summer 69; Winter 69; Summer 70; Winter 70
1971 Edition: Addenda Summer 71; Winter 71; Summer 72; Winter 72; Summer 73; Winter 73
1974 Edition: Addenda Summer 74; Winter 74; Summer 75; Winter 75; Summer 76; Winter 76
1977 Edition: Addenda Summer 77; Winter 77; Summer 78; Winter 78; Summer 79; Winter 79
1980 Edition: Addenda Summer 80;
1981 Edition: Addenda Winter 1981
1983 Edition: Addenda Summer 83; Winter 83; Summer 84; Winter 84; Summer 85; Winter 85
1986 Edition: 1986, 1987 and 1988 Addenda
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
ASME Boiler and Pressure Vessel Code, Section III, Division 1, 1997 Addenda, 1998 Edition, 1999 Addenda and 2000 Addenda
ASME Boiler and Pressure Vessel Code, Section III, Division 1, 2001 Edition, 2002 and 2003 Addenda
ASME Boiler and Pressure Vessel Code Section III, 1980 Edition: Subarticle CC–3720, Division 2
Subarticle NE–3220
ASME Boiler and Pressure Vessel Code Section XI, Division 1, 1970 Edition: Addenda Winter 70
1980 Edition: Addenda Winter 80
1981 Edition: Addenda Winter 81; Winter 82
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
ASME Boiler and Pressure Vessel Code, Section XI, Division 1, 1997 Addenda, 1998 Edition, 1999 Addenda, and 2000 Addenda
ASME Boiler and Pressure Vessel Code, Section XI, Division 1, 2001 Edition, 2002 and 2003 Addenda
ASME Code for Operation and Maintenace of Nuclear Power Plants (OM Code) 1995 Edition, 1996 Addenda
ASME Code for Operation and Maintenace of Nuclear Power Plants (OM Code) 1997 Addenda, 1998 Edition, 1999 Addenda and 2000 Addenda
ASME Code for Operation and Maintenace of Nuclear Power Plants (OM Code) 2002 and 2003 Addenda
Draft ASME Code for Pumps and Valves for Nuclear Power, dated 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
Part 50, App. K, I.C.1.b.
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
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
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
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
IEEE 803–1983 Recommended Practices for Unique Identification in Power Plants and Related Facilities—Principles and Definitions
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
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
NRC Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, dated June 2003