FireDOC Search

displaying 41 - 50 results in total 55

  • Burton, J. L.
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    Fire Protection Requirements. PRA and Regulatory Reform.
    Gulf States Utilities Co., St. Francisville, LA
    NUREG/CP-0129
    NUREG/CP-0129
    U.S. Nuclear Regulatory Commission and Scientech, Inc. Proceedings of the Workshop on Program for Elimination of Requirements Marginal to Safety. April 27-28, 1993, Bethesda, MD, Dey, M.; Arsenault, F.; Patterson, M.; Gaal, M., Editors, 72-78 p., 1993

  • George, H.
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    Fire Protection Requirements. Alternate Approaches for Appendix R/Fire Protection.
    SYNERGY Consulting Services, Chevy Chase, MD
    NUREG/CP-0129
    NUREG/CP-0129
    U.S. Nuclear Regulatory Commission and Scientech, Inc. Proceedings of the Workshop on Program for Elimination of Requirements Marginal to Safety. April 27-28, 1993, Bethesda, MD, Dey, M.; Arsenault, F.; Patterson, M.; Gaal, M., Editors, 78-81 p., 1993

  • Trubatch, S. L.
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    Fire Protection Requirements.
    Winston and Straw, Washington, DC
    NUREG/CP-0129
    NUREG/CP-0129
    U.S. Nuclear Regulatory Commission and Scientech, Inc. Proceedings of the Workshop on Program for Elimination of Requirements Marginal to Safety. April 27-28, 1993, Bethesda, MD, Dey, M.; Arsenault, F.; Patterson, M.; Gaal, M., Editors, 81-83 p., 1993

  • Mawby, F. D.; Haighton, A. P.
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    Approach Adopted in England and Wales in Defining the Level of Fire Safety at Nuclear Power Stations.
    Nuclear Electric plc, Manchester, England
    Fire Research Station and the Institute of Fire Safety in association with the Fire Service Research and Training Trust. Fire Safety by Design: A Framework for the Future. Proceedings. Technical Conference. Featuring the Combined 1993 Fire Research Lecture and IFS Inaugural Lecture. November 10, 1993, Borehamwood, England, 1-14 p., 1993

  • Powers, C. S.
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    Safety Analysis Report 231-Z Building.
    Battelle Pacific Northwest Lab., Richland, WA
    BNWL-CC-1924
    BNWL-CC-1924
    March 1989
    81 p.

  • EG&G Idaho, Inc.
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    Summary of Tiger Team Assessment and Technical Safety Appraisal Recurring Concerns in the Training Area.
    EG&G Idaho, Inc., Idaho Falls, ID
    EGG-OTTA-10636
    Department of Energy, Washington, DC, EGG-OTTA-10636
    January 1993
    19 p.

  • U.S. Nuclear Regulatory Commission
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    NRC Safety Research in Support of Regulation, FY 1993.
    Nuclear Regulatory Commission, Washington, DC
    NUREG-1266, Vol. 8
    NUREG-1266, Vol. 8
    June 1994
    89 p.

  • Kersting, E.; vonLinden, J.; Muller-Ecker, D.; Werner, W.
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    Safety Analysis for Boiling Water Reactors: A Summary.
    Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) mbH, Koeln, Germany
    GRS-98
    GRS-98
    July 1993
    110 p.

  • U.S. Nuclear Regulatory Commission
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    NRC Safety Research in Support of Regulation, FY 1994.
    Nuclear Regulatory Commission, Washington, DC
    NUREG-1266, Vol. 9
    NUREG-1266, Vol. 9
    1995 1994
    88 p.

  • O'Brien, D.; Fischer, S. R.; Gerdes, E. R.
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    Quantitative Hazard Assessment of a U.S. Department of Energy Nuclear Explosive Operation.
    Los Alamos National Laboratory, NM
    Probabilistic Safety Assessment Topical Meeting. PSA '96. Proceedings. September 29-October 3, 1996, Park City, UT, 1-11 p., 1996