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 Entered dateSiteRegionReactor typeEvent description
ENS 5495820 October 2020 15:20:00Purdue UniversityNRC Region 0During the course of operations, a potential error in the power calibration of the PUR-1, License Number R-87, was discovered. This calibration error would result in a special report requirement as specified in ((Technical Specification)) TS 6.7.b.1.c.vi, which is that an observed inadequacy in the implementation of a procedural control such that this inadequacy could have caused the development of an unsafe condition with regards to reactor operations. By extension the miscalibration caused a true reactor power higher than the measured reactor power. As such, this likely resulted in the operation in violation of the limiting condition for operation as established in TS Section 3 Table I and operation with an actual safety system setting for a required system less conservative than the limiting safety system settings specified in the Technical Specifications. These reporting requirements are Part i. and ii. of TS 6.7.b.1.c. The calibration error implicates a violation of the maximum licensed power level of 12 kW. The Safety Limit was not exceeded at any point.
ENS 533219 April 2018 14:48:00Purdue UniversityNRC Region 0On April 6, 2018 at approximately 1500 EDT, it was determined there was a potential Reportable Occurrence at the PUR-1 facility. There were no unsafe conditions at any time. The PUR-1 Technical Specification 6.7.b.1.c.vi reads, 'An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations.' A visual inspection of the fuel is required annually with no interval to exceed 15 months. While the reactor has not operated and has remained in shutdown condition since June 5, 2017, this surveillance had not occurred for 20 months as of March, 2018. This surveillance was performed on March 27, 2018 but the administrative control which should have prevented the extended interval was not observed by facility staff. There was no existence of unsafe conditions and no (reactor) operations at any time during the period in question.