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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- IR 05000293/2014008 +
- IR 05000321/2014005 +
- ML15030A008 +
- ML14247A545 +
- ML14349A518 +
- IR 05000057/2014001 +
- ML15027A184 +
- TAC:MF4692 +
- ML15033A381 +
- ML15033A373 +
- ML15040A639 +
- ML15041A051 +
- TAC:MF5741 +
- ML15043A408 +
- NLS2015006, Enclosure 2 to NLS2015006: SL-012450, Rev. 0, Cooper Nuclear Station Flood Hazard Reevaluation Report, Page 2-91 Through End +
- ML15041A470 +
- ML15041A469 +
- Press Release-IV-15-004, NRC Names New Resident Inspector at Callaway Nuclear Plant +
- ML15036A026 +
- ML15036A025 +
- NL-15-010, Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3 +
- SVPLTR 15-0009, Request for Relaxation of Condition V(A)(A.1 (1)) of Confirmatory Order EA-13-068 +
- NG-14-0291, License Amendment Request (TSCR-1 51) for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control +
- ML15029A476 +
- 1CAN011506, Responses to Request for Additional Information Time Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years +
- NL-15-0080, Special Report 2015-001-00 +
- ML15027A318 +
- ML15027A041 +
- ML15026A729 +
- Press Release-IV-15-003, NRC Begins Special Inspection at River Bend Station +
- ULNRC-06176, Request I4R-02 for Relief from Requirements of ASME Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports +
- NRC-15-0008, DTE Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 13 +
- ML15022A653 +
- ML15006A360 +
- ML15002A162 +
- ML14247A558 +
- 1CAN011506, Arkansas Nuclear One, Unit 1 - Responses to Request for Additional Information Time Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years +
- NRC-2015-0010, Crystal River Unit - FRN, Exemption from the Requirements of 10 CFR Sections 50.82 and 50.75 Related to Use of the Decommissioning Trust Fund for Irradiated Fuel Management and Site Restoration +
- MNS-15-002, Response to August 28, 2014, & October 27, 2014, NRC Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program +
- ML20247J496 +
- 05000259/LER-2014-006, Regarding Main Steam Relief Valves Lift Settings Outside Technical Specifications Required Setpoint +
- IR 05000390/2014501 +
- IR 05000327/2014501 +
- 05000269/LER-2014-002, Regarding Deficiency in Loss of Coolant Accident Analysis Adversely Affected Predicted Peak Cladding Temperature +
- ML15090A269 +
- ML15021A451 +
- ML15020A430 +
- ML15027A576 +
- OI 4-2013-032, Closure of Investigation (OI 4-2013-032) +
- ML15090A267 +