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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Remembering ANS member Gil Brown
Brown
The nuclear community is mourning the loss of Gilbert Brown, who passed away on July 11 at the age of 77 following a battle with cancer.
Brown, an American Nuclear Society Fellow and an ANS member for nearly 50 years, joined the faculty at Lowell Technological Institute—now the University of Massachusetts–Lowell—in 1973 and remained there for the rest of his career. He eventually became director of the UMass Lowell nuclear engineering program. After his retirement, he remained an emeritus professor at the university.
Sukesh Aghara, chair of the Nuclear Engineering Department Heads Organization, noted in an email to NEDHO members and others that “Gil was a relentless advocate for nuclear energy and a deeply respected member of our professional community. He was also a kind and generous friend—and one of the reasons I ended up at UMass Lowell. He served the university with great dedication. . . . Within NEDHO, Gil was a steady presence and served for many years as our treasurer. His contributions to nuclear engineering education and to this community will be dearly missed.”
Rossnyev Alvarado, Steven A. Arndt (NRC)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 983-992
As microprocessor-based safety systems were first introduced in nuclear power plants in the US in the 1980s, the U.S. Nuclear Regulatory Commission (NRC) recognized that digital instrumentation and control (DI&C) can provide advantages in reliability and functionality, but that it also creates the potential for a new vulnerability to a common cause failures (CCFs) among systems in which functions are performed by identical software executed in identical hardware. Specifically, the staff recognized that a latent, systemic fault in design or implementation of software could result in the concurrent failure of essential safety or compensating systems. The potential for pervasive and latent systemic faults resulting in a CCF could be more significant for DI&C systems because of increased resource sharing and the potential for unspecified interactions or unanalyzed conditions. In SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs,” dated April 2, 1993 [1], the NRC staff identified policy, technical, and licensing issues pertaining to evolutionary and advanced light water reactor designs, one of which was defense against CCF in DI&C systems. The staff presented position recommendations for addressing the potential for CCFs in DI&C safety systems. In the Staff Requirements Memorandum (SRM) to SECY SECY-93-087 [2], the Commission approved, in part, and disapproved, in part, the staff’s recommendation. The NRC staff implemented the Commission direction into staff guidance for the review of digital I&C systems in a Branch Technical Position (BTP) 7-19, “Guidance for Evaluation of Defense-in-Depth and Diversity in Digital Computer-Based Instrumentation and Control Systems,” [3] in the Standard Review Plan used for new digital systems for new reactors and operating reactors. In the SRM to SECY 16-0070 [4], “Integrated Strategy to Modernize the Nuclear Regulatory Commission’s Digital Instrumentation and Control Regulatory Infrastructure”, dated October 25, 2016, the Commission approved implementation of the staff’s integrated action plan (IAP) to modernize the NRC’s digital instrumentation and control regulatory infrastructure. As part the work outlined in the IAP NRC staff has reviewed the current NRC position on defense against CCF in digital I&C systems. This paper outlines the high level principles the staff will be using to update the CCF guidance based on current Commission direction.
