Aging Reactors
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NIRS presented to NRC Safety Research Conference on a panel discussion of “Material Degradation: Present and Future Directions” where NIRS revealed that a federal laboratory tests of mock-ups of the severely corroded as found Davis-Besse reactor pressure vessel head burst at less than the reactor’s normal operational pressure.
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NIRS comments to U.S. Nuclear Regulatory Commission regarding the Generic Environmental Impact Statement for reactor license extensions or license renewal.
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NIRS fact sheet focuses on the sudden and unexpected discovery of cracking of stainless steel penetration sleeves in the bottom reactor vessel head at South Texas Project nuclear generating station.
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NIRS comments to NRC in support of communications that strengthen requirements for inspection of deteriorating steam generator tubes in Pressurized Water Reactors.
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NIRS letter to NRC Commission Chair Nils Diaz in follow-up to NIRS presentation to NRC Commissioners February 2003 conveying continued concern that the federal nuclear safety agency has not learned the most significant lesson from the near miss accident at Davis-Besse nuclear station (2002) regarding failure to enforce safety guidelines and an agency Order in a gamble to give FirstEnergy more production time.
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NIRS speech to the U.S. Nuclear Regulatory Commission Regulatory Information Conference workshop focuses on material degradation of reactor internal components.
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NIRS presented to the Commissioners of the U.S. Nuclear Regulatory Commission its concerns with the near-miss accident of the Davis-Besse nuclear power station and the agency’s abandonment of its safety principles for an industry production agenda.
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