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Issue date | Title | Topic | |
---|---|---|---|
NRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis | 7 March 2023 | License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis | Safe Shutdown Earthquake Channel-control blade interference |
ML22301A174 | 28 October 2022 | Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) | |
NRC-20-0009, DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR) | 8 June 2020 | DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR) | Hydrostatic Finite Element Analysis Pressure and Temperature Limits Report |
NRC-20-0010, Submittal of Plant Specific Emergency Core Cooling System (ECCS) Evaluation Model Reanalysis. Non-Proprietary GE Hitachi Nuclear Energy Report NEDO-33919 Enclosed | 8 April 2020 | Submittal of Plant Specific Emergency Core Cooling System (ECCS) Evaluation Model Reanalysis. Non-Proprietary GE Hitachi Nuclear Energy Report NEDO-33919 Enclosed | Stroke time MELLLA Fuel cladding |
NRC-15-0011, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 17 | 12 February 2015 | Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 17 | |
ML14204A709 | 23 July 2014 | Enclosure 3, Affidavit of Peter M. Yandow | |
ML112700068 | 26 September 2011 | Enclosure 3, Mfn 10-245 R4, Affidavit | Channel-control blade interference |
ML060170279 | 9 December 2005 | BWROG Affidavit | |
ML052000328 | 14 July 2005 | Surveillance Program for Channel-Control Blade Interference | Channel-control blade interference |
NRC-05-0033, Transmittal of the RPV Neutron Flux Evaluation Report in Support of the Request to Revise the Reactor Coolant System Pressure and Temperature Limit Curves in Technical Specification 3.4.10 | 15 April 2005 | Transmittal of the RPV Neutron Flux Evaluation Report in Support of the Request to Revise the Reactor Coolant System Pressure and Temperature Limit Curves in Technical Specification 3.4.10 | Hydrostatic |