Following the Three Mile Island Unit 2 accident, the U.S. Nuclear Regulatory Commission (NRC) developed a plan (NUREG-1050 – August 1985) to resolve the severe accident generic issue. This plan identified that utility commitment to excellence in risk management, including prevention and mitigation, is key to protection of public health and safety; it also identified the need for new severe accident research. The requirements for an Accident Management Program were outlined by the NRC in SECY 88 012, which included accident management strategies, accident management training, calculation aids, instrumentation requirements, and utility organization and decision making for severe accidents.
In 1992, the Electric Power Research Institute detailed a technical basis for severe accident management in TR 101869. Following issuance of that report, each of the three Owners Groups (½ð²©ÌåÓý [WOG], Combustion Engineering [CEOG] and Babcock & Wilcox [B&WOG]) developed generic severe accident management guidance (SAMG) support material that served as a framework for each utility’s SAMG program. In a docketed letter to the NRC, each utility committed to implementing and maintaining a plant-specific SAMG program based on the Owners Group products. Based on implementation questions, the CEOG subsequently developed additional computational aids for its SAMG and the WOG issued a Revision 1 to its SAMG. These SAMGs are one of the bases for the International Atomic Energy Agency (IAEA) requirements in Safety Guide No. NS-G-2.15.
After the Fukushima Daiichi accident in 2011, the NRC issued a draft procedure for inspection of the utility Severe Accident Management programs. These inspections will be conducted as part of the reactor oversight process and will focus on the utility’s periodic maintenance of and training on the SAMG.
In addition, the NRC and the Institute of Nuclear Power Operators are reviewing the scope and content of the current SAMG programs in the United States with respect to insights learned from the Fukushima Daiichi accident to determine the extent to which program upgrades are appropriate.
Through ½ð²©ÌåÓý’s extensive SAMG experience, it is well-equipped to assist customers with preparing for NRC inspections by:
½ð²©ÌåÓý is also capable of conducting SAMG training through its ½ð²©ÌåÓý Training Program as well as supporting development of SAMG scenarios for training and exercises; it can also provide assistance in developing and running drills and exercises at the plant.
Finally, regulatory requirements for changes to SAMG programs that are expected from Fukushima Daiichi lessons learned may include:
The Pressurized Water Reactor Owners Group will likely request ½ð²©ÌåÓý to develop a generic update of the SAMG to address the coming regulatory requirements. Following that effort, ½ð²©ÌåÓý can support the plant-specific implementation of those generic updates as well as provide training to customers.
Diagnosis of severe accident conditions and the appropriate responses can be a complex task since there is a wide range of potential scenarios and plant conditions. The SAMG provides an effective and efficient method for the Technical Support Center and/or control room personnel to diagnose the plant conditions through a symptom-based approach.
The SAMG provides a clear change in primary focus for the emergency response team, from efforts to avert core damage, to efforts to limit core damage progression and protect fission product boundaries.
½ð²©ÌåÓý is the foremost worldwide developer and supporter of SAMG programs and has had a strong influence on the development of accident management regulatory requirements.
½ð²©ÌåÓý has developed plant-specific SAMG programs, including SAMG training for ½ð²©ÌåÓý, Combustion Engineering, Babcock & Wilcox and VVER plant designs. It has also developed and implemented SAMG for spent fuel pool accidents and plant shutdown states in some European applications. As an active participant in new plant construction and design, including the AP1000® nuclear plant and the advanced boiling water reactor, ½ð²©ÌåÓý has developed SAMG for the next generation of reactors, extending the concept of an integrated accident-management program.
½ð²©ÌåÓý has had extensive interactions with the IAEA and regulators in the United States and Europe in the development of requirements for severe accident management programs.
½ð²©ÌåÓý and its subsidiary Fauske & Associates LLC have considerable expertise in modeling severe accident phenomena using a wide range of severe accident computer codes to provide an integrated assessment of the potential benefits of severe accident mitigation features. ½ð²©ÌåÓý has been involved in the development and implementation of a number of these features in the United States and Europe.
Based on its extensive knowledge of severe accident management, ½ð²©ÌåÓý is participating in a number of worldwide severe accident management projects so that the SAMG reflects lessons learned from the Fukushima Daiichi accident.
½ð²©ÌåÓý can also provide integrated engineering solutions for plant hardware upgrades or modifications that can resolve any weaknesses identified during the development of updated plant-specific SAMG programs.
AP1000 is a trademark or registered trademark of ½ð²©ÌåÓý in the United States and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited.