FireDOC Search

displaying 311 - 320 results in total 492

• Lambright, J.; Lynch, J.; Bohn, M.; Ross, S.; Brosseau, D.
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  Evaluation of Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment. Appendices E and F.
  Sandia National Laboratories, Albuquerque, NM; Science and Engineering Associates, Inc., Albuquerque, NM; ERCE, Inc., Albuquerque, NM
  SAND90-1507-VOL-4
  Nuclear Regulatory Commission, Washington, DC, SAND90-1507-VOL-4
  December 1992
  279 p.

• Lambright, J.; Lynch, J.; Bohn, M.; Ross, S.; Brosseau, D.
  view article (1.0)

  Evaluation of Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment. Main Report.
  Sandia National Laboratories, Albuquerque, NM; Science and Engineering Associates, Inc., Albuquerque, NM; ERCE, Inc., Albuquerque, NM
  SAND90-1507-VOL-1
  Nuclear Regulatory Commission, Washington, DC, SAND90-1507-VOL-1
  December 1992
  221 p.

• Payne, A. C., Jr.; Eide, S. A.; LaChance, J. C.; Whitehead, D. W.
  view article (1.0)

  Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP). Initiating Events and Accident Sequence Delineation.
  Sandia National Labs., Albuquerque, NM
  SAND92-0537-VOL-4
  Nuclear Regulatory Commission, Washington, DC, SAND92-0537-VOL-4
  October 1992
  118 p.

• Lambright, J. A.; Brosseau, D. A.; Payne, A. C., Jr.; Daniel, S. L.
  view article (1.0)

  Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP). Internal Fire Analysis.
  Sandia National Labs., Albuquerque, NM
  SAND92-0537-VOL-9
  Nuclear Regulatory Commission, Washington, DC, SAND92-0537-VOL-9
  March 1993
  715 p.

• Antaki, G. A.; Flanders, H. E.; Thomas, B. D.
  view article (1.0)

  Evaluation of Seismic Interactions: Guidelines and Application.
  Westinghouse Savannah River Co., Aiken, SC
  WSRC-MS-92-068
  Department of Energy, Washington, DC, WSRC-MS-92-068
  1992
  10 p.
  American Society of Mechanical Engineers. Pressure Vessels and Piping Conference. June 22-26, 1992, New Orleans, LA, 1992

• Allenspach, F.
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  Historical Data Summary of the Systematic Assessment of Licensee Performance. Revision 10. Technical Report. January 1-June 30, 1992.
  Nuclear Regulatory Commission, Washington, DC
  NUREG-1214-REV-10
  NUREG-1214-REV-10
  August 1992
  125 p.

• Tossavainen, K.
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  Operation of Finnish Nuclear Power Plants. 2nd Quarterly Report.
  Finnish Center for Radiation and Nuclear Safety, Helsinki, Finland
  STUK-B-YTO-90
  STUK-B-YTO-90
  December 1991
  30 p.

• Majumdar, K. C.; Alesso, H. P.; Altenbach, T. J.
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  On Fire Risk/Methodology for the Next Generation of Reactors and Nuclear Facilities.
  Lawrence Livermore National Laboratory, CA
  UCRL-JC-110420
  Department of Energy, Washington, DC, UCRL-JC-110420
  October 15, 1992
  7 p.
  American Nuclear Society Meeting. January 27-29, 1993, Clearwater, FL, ['1992', '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

• Muller, K.
  view article (1.0)

  Experience on Verification of Fire Simulation Codes.
  Kemforschungszentrum Karlsruhe, Germany
  VTT-Technical Research Center of Finland and Forum for International Cooperation in Fire Research. Nordic Fire Safety Engineering Symposium. Development and Verification of Tools for Performance Codes. August 30-September 1, 1993, Espoo, Finland, 1-10 p., 1993