A qualitative assessment of current CCF guidance based on a review of safety system digital implementation changes with evolving technology - 148
Creators
- 1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831 (United States)
- 2. The University of Tennessee, Circle Park Dr., Knoxville, TN, 37996 (United States)
Description
This paper is a summary of a study performed in support of the US Nuclear Regulatory Commission (NRC) to evaluate current policy on software common-cause failure (CCF). The study reported in this paper is one of several that contributed to the technical basis to inform NRC staff. The study first reviewed policies and assessment guidance as discussed in the Staff Requirements Memorandum to the Secretary of the Commission, Office of the NRC (SECY) 93-087, Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor (ALWR) Designs, and Branch Technical Position (BTP) 7-19, Guidance on Evaluation of Defense-in-Depth and Diversity in Digital Computer-Based Instrumentation and Control Systems, as well as Chapter 7, 'Instrumentation and Controls', in NUREG-0800, Standard Review Plan for Review of Safety Analysis Reports for Nuclear Power Plants. The study then examined instrumentation and controls (I and C) technology implementations in nuclear power plants in the light of current CCF guidance. The intent was to assess whether the current position on CCF remains appropriate given the evolutions in digital safety system implementations and, if gaps in the guidance were found, to provide recommendations as to how these gaps could be closed. The methodology adopted was to review the vendors' technology and software implementation processes for digital safety systems as technology evolved. The following three representative safety systems were selected to provide illustrative examples: - Eagle 21 was selected to represent vintage microprocessor-based technology used from the 1980's to mid-1990's, - TELEPERM XS (TXS) was selected to represent second generation microprocessor-based technology used from the mid-1990's to the 2000's, and - The advanced logic system (ALS) was selected to represent the latest trend of using technology based on field programmable gate arrays (FPGAs). Technology implementations were reviewed in light of the basic premise of the NRC in BTP 7-19 (Revision 6), that software-based or software-logic-based digital system development errors are a credible source of CCF and therefore are susceptible to CCF because identical copies of the software-based logic and architecture are present in redundant divisions of safety-related systems. BTP 7-19 categorizes firmware and logic developed from software-based development systems all under software. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 7 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075660
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; DIGITAL COMPUTERS; DIGITAL SYSTEMS; IMPLEMENTATION; MICROPROCESSORS; REACTOR CONTROL SYSTEMS; REACTOR LICENSING; RECOMMENDATIONS; SAFETY ANALYSIS; SAFETY STANDARDS; US NRC; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- COMPUTERS; CONTROL SYSTEMS; ELECTRONIC CIRCUITS; LICENSING; MICROELECTRONIC CIRCUITS; NATIONAL ORGANIZATIONS; REACTOR LIFE CYCLE; REACTORS; STANDARDS; US ORGANIZATIONS
Optional Information
- Notes
- 4 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)