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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

• ML20114E006  + (ML20114E006)
• L-92-235, Forwards Rev 8 to St Lucie Safeguards Contigency Plan.Encl Withheld (Ref 10CFR2.790(a)(3))  + (ML20114E007)
• ML20114E009  + (ML20114E009)
• ML20114E011  + (ML20114E011)
• ML20114E014  + (ML20114E014)
• ML20114E015  + (ML20114E015)
• ML20114E019  + (ML20114E019)
• ML20114E039  + (ML20114E039)
• ML20114E059  + (ML20114E059)
• ML20114E060  + (ML20114E060)
• ML20114E061  + (ML20114E061)
• PMNS20200419, Public Seminar to Discuss Temporary Regulatory Relief Pathways for Non-Medical NRC Radioactive Materials Licensees During the COVID-19 Public Health Emergency  + (ML20114E062)
• ML20114E063  + (ML20114E063)
• ML20114E065  + (ML20114E065)
• IR 05000287/2002015  + (ML20114E069)
• ML20114E071  + (ML20114E071)
• ML20114E073  + (ML20114E073)
• PMNS20200263, NRC Staff Questions on NEDC-33910P BWRX-300 Reactor Pressure Vessel Isolation and Overpressure Protection  + (ML20114E089)
• ML20114E094  + (ML20114E094)
• ML20114E096  + (ML20114E096)
• PMNS20200244, NRC Staff Questions on NEDC-33910P BWRX-300 Reactor Pressure Vessel Isolation and Overpressure Protection  + (ML20114E099)
• PMNS20200262, NRC Staff Questions on NEDC-33910P BWRX-300 Reactor Pressure Vessel Isolation and Overpressure Protection  + (ML20114E101)
• ML20114E106  + (ML20114E106)
• RA-20-0117, Supplemental Information for License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits  + (ML20114E131)
• IR 05000255/2001008  + (ML20114E132)

• ML20114E135  + (ML20114E135)

• PMNS20200245, NRC Staff Questions on NEDC-33910P BWRX-300 Reactor Pressure Vessel Isolation and Overpressure Protection  + (ML20114E138)
• STC-20-036, Letter for Notice of Intent to Conduct Scoping and Prepare an Advanced Nuclear Reactor Generic Environmental Impact Statement  + (ML20114E140)
• ML20114E142  + (ML20114E142)
• PMNS20200450, Pre-Submittal Meeting Regarding Vogtle, Units 1 and 2, Proposed Licensing Actions for a Risk-Informed Resolution to Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance  + (ML20114E144)
• ML20114E147  + (ML20114E147)
• ML20114E150  + (ML20114E150)
• ML20114E157  + (ML20114E157)
• SECY-19-0116, M200423: Affirmation Session - SECY-19-0098/19-0098A, Florida Power & Light Co; SECY-19-0109, Direct Final Rule on Social Security Number Fraud Prevention; SECY-19-0116, Holtec Intl; SECY-19-0122, Firstenergy Nuclear Operating Company  + (ML20114E158)
• ML20114E159  + (ML20114E159)
• ML20114E161  + (ML20114E161)
• ML20114E165  + (ML20114E165)
• ML20114E169  + (ML20114E169)
• ML20114E170  + (ML20114E170)
• SECY-19-0098, SRM-M200423: Affirmation Session - SECY-19-0098/19-0098A - Fl Pwr & Light Co.; SECY-19-0109 - Direct Final Rule - SSN Fraud Prevention; SECY-19-0116 - Holtec International; SECY-19-0122 - Firstenergy Nucl. Operating Co. and Firstenergy  + (ML20114E186)
• VR-SECY-19-0109, SRM-M200423: Enclosure 1 - Direct Final Rule - Social Security Number Fraud Prevention  + (ML20114E188)
• 05000341/LER-2020-001, Secondary Containment Inoperable Due to Both Airlock Doors Open  + (ML20114E190)
• ML20114E191  + (ML20114E191)
• ML20114E194  + (ML20114E194)
• ML20114E195  + (ML20114E195)
• ML20114E196  + (ML20114E196)
• ML20114E198  + (ML20114E198)
• ML20114E199  + (ML20114E199)
• ML20114E200  + (ML20114E200)
• ML20114E201  + (ML20114E201)
• IR 05000311/1999010  + (ML20114E204)