NUREG/CR-6850, Volume 1 - NRC

ACKNOWLEDGMENTSThis work benefited from contributions and considerable technical support from Dominion,American Electric Power, Pacific Gas & Electric, Duke Power, Exelon Corporation, FloridaPower & Light, Southern California Edison, Nuclear Management Corporation, and theCANDU Owners Group. The methodology developed was tested at three nuclear facilities in theU.S. The authors extend their gratitude to the staff of these facilities for their support and forsharing their insights gained from use of the methodology. The process benefited significantlyfrom their input.John Spaargaren (Dominion, Millstone)Paul Raimondi (Dominion, Millstone)Joseph Mangeno (Dominion, Millstone)Fred Ceitek (Dominion, Millstone)Rasool Baradaran (AEP, DC Cook)Richard Gray (AEP, DC Cook)Amir Afzali (PG&E, Diablo Canyon)Clarence Worrell (PG&E, Diablo Canyon)The following individuals served on a peer review team that provided review and comments onthe interim and final report of this project.Dennis Henneke (Duke Power)Christopher Pragman (Exelon Corp.)Ching Guey (Florida Power & Light)Sam Chien and Parviz Moini (Southern California Edison)Robert Ladd (NMC – Point Beach)Keith Dinnie (formerly with CANDU Owners Group, COG)The authors extend particular gratitude to Dennis Henneke of Duke Power and Chris Pragman ofExelon Corp. for their tireless review of multiple revisions of the task procedures. Their effortscontributed substantially to the quality and completeness of the final product.The authors also gratefully acknowledge the technical contributions of Professor Ali Mosleh(University of Maryland) in the development of the fire ignition frequency and uncertaintymethods and Dennis Bley (Buttonwood Consulting Inc.) in the development of the post-firehuman reliability analysis approach.xix