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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

• ML14071A159  + (ML14071A159)
• ML14071A167  + (ML14071A167)
• ML14071A169  + (ML14071A169)
• PMNS20140424, Public Meeting Agenda by NRR - Discussion of Electrical Issues Between NRC Staff and TVA, the Licensee for SQN, Units 1 and 2, to Aid NRC Staff in Evaluating the Improved TSs Conversion Submittal  + (ML14071A172)
• ML14071A181  + (ML14071A181)
• ML14071A183  + (ML14071A183)
• ML14071A198  + (ML14071A198)
• ML14071A203  + (ML14071A203)
• ML14071A207  + (ML14071A207)
• ML14071A233  + (ML14071A233)
• ML14071A242  + (ML14071A242)
• ML14071A248  + (ML14071A248)
• GNRO-2014/00025, Draft Plant-Specific Supplement 50 to the Generic Environmental Impact Statement for License Renewal  + (ML14071A249)
• ML14071A261  + (ML14071A261)
• ML14071A262  + (ML14071A262)
• 05000285/LER-2014-002, Regarding Reactor Manual Trip Due to Control Rod Misalignment  + (ML14071A277)
• RS-14-056, Extension Request - Response to March 12, 2012 Request for Information on Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report  + (ML14071A278)
• ML14071A282  + (ML14071A282)
• ML14071A290  + (ML14071A290)
• 05000482/LER-2014-001, Regarding Failure to Comply with Required Action of Technical Specification 3.4.3 While Performing a Vacuum Fill of the Reactor Coolant System  + (ML14071A304)
• ML14071A306  + (ML14071A306)
• ML14071A307  + (ML14071A307)
• ML14071A314  + (ML14071A314)
• ML14071A315  + (ML14071A315)
• ML14071A316  + (ML14071A316)

• ML14071A318  + (ML14071A318)

• ML14071A331  + (ML14071A331)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-6 Through Page 2-17  + (ML14071A331)
• ML14071A332  + (ML14071A332)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-35 Through Page 2-55  + (ML14071A332)
• ML14071A333  + (ML14071A333)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-18 Through Page 2-34  + (ML14071A333)
• ML14071A335  + (ML14071A335)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-56 Through Page 2-93  + (ML14071A335)
• ML14071A336  + (ML14071A336)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-94 Through Page 2-98  + (ML14071A336)
• ML14071A338  + (ML14071A338)
• ML14071A339  + (ML14071A339)
• ML14071A376  + (ML14071A376)
• ML14071A378  + (ML14071A378)
• ML14071A393  + (ML14071A393)
• ML14071A400  + (ML14071A400)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 1-8 Through Page 2-5  + (ML14071A400)
• ML14071A401  + (ML14071A401)
• LR-N14-0042, Salem, Units 1 & 2, Pseg Nuclear Llc'S Response to Request for Information Regarding Flooding Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Generating Station Flood Hazard  + (ML14071A401)
• ML14071A402  + (ML14071A402)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Cover Through Page 1-4  + (ML14071A402)
• ML14071A403  + (ML14071A403)
• LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 1-5 Through Page 1-7  + (ML14071A403)
• NRC 2014-0016, Submittal of License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)- Response to Request for Additional Information  + (ML14071A405)
• ML14071A410  + (ML14071A410)