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Developing a new regulatory framework for advanced reactors: Update on Part 53
White
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) on March 29 held another presentation in its monthly Community of Practice (CoP) series. The presenter, Patrick White with the Nuclear Innovation Alliance (NIA), talked about the current status of efforts to develop a new regulatory framework for advanced reactors—known as 10 CFR Part 53 or simply Part 53. White serves as the research director of the NIA, where he leads their research as well as analysis-based stakeholder and policymaker engagement and education. White’s March 29 presentation is publicly available on YouTube and at ANS’s publication platform Nuclear Science and Technology Open Research (NSTOR).
RP3C chair N. Prasad Kadambi opened the CoP with brief introductory remarks about the RP3C before he welcomed White as the session’s presenter.
White covered three main topics: the history of the existing regulatory frameworks for new reactors, progress to date on the development of the Part 53 rule for advanced reactors, and the current status and next steps for the Part 53 rulemaking process.
Hiroo Igarashi, Nobuyuki Ohta, Naoshi Usui, Katsumi Ohsumi, Shunsuke Uchida, Tsuneo Matsui
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 92-102
Technical Paper | Nuclear Plant Operation and Control | doi.org/10.13182/NT01-A3161
Articles are hosted by Taylor and Francis Online.
A system has been developed for evaluating the effect of impurity intrusion on reactor water as part of the chemistry diagnostic system for boiling water reactor water. Past records of anomalous changes noted in reactor water quality were first surveyed to identify the substances presenting the highest probability of intrusion into reactor water. The ions and their concentrations were derived, taking into account mutual chemical reactions among the substances and the plant operating conditions affecting the balance equation of the reactor primary system.The results predicted for the peak conductivity of reactor water during plant startup were within ±15% of the measured data. This good agreement found on a comparison of estimated results with measured data from an actual plant substantiated the validity of the present method.
