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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

• ML24074A382  + (ML24074A382)
• ML24074A387  + (ML24074A387)
• ML24074A388  + (ML24074A388)
• ML24074A392  + (ML24074A392)
• ML24074A397  + (ML24074A397)
• Inspection Manual Change Notice 24-010, Table of Contents for Inspection Manual Change Notice 24-010  + (ML24074A399)
• ML24074A409  + (ML24074A409)
• ML24074A416  + (ML24074A416)
• ML24074A417  + (ML24074A417)
• ML24074A418  + (ML24074A418)
• ML24074A419  + (ML24074A419)
• IR 05000298/2024090  + (ML24074A424)
• ML24074A425  + (ML24074A425)
• ML24074A426  + (ML24074A426)
• ML24074A427  + (ML24074A427)
• ML24074A433  + (ML24074A433)
• RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations  + (ML24074A437)
• PMNS20240328, Probabilistic Risk Assessment (PRA) Configuration Control (Pcc) Significance Determination Process (SDP) Meeting  + (ML24074A444)
• ML24074A449  + (ML24074A449)
• ML24074A453  + (ML24074A453)
• PMNS20240377, Meeting with Oklo to Discuss Physical Security for Its Advanced Reactor Design  + (ML24074A455)
• CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37  + (ML24074A457)
• ML24074A459  + (ML24074A459)
• ML24074A460  + (ML24074A460)
• ML24074A461  + (ML24074A461)

• ML24074A463  + (ML24074A463)

• NRC-2023-0174, Comment (1) of Anonymous Individual on Accelerated Decommissioning Partners Crystal River Unit 3, LLC; Crystal River Unit 3; License Termination Plan  + (ML24074A464)
• ML24074A466  + (ML24074A466)
• ML24074A467  + (ML24074A467)
• ML24074A470  + (ML24074A470)
• ML24074A472  + (ML24074A472)
• ML24074A473  + (ML24074A473)
• IR 05000458/2024040  + (ML24074A476)
• RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS  + (ML24075A001)
• ML24075A006  + (ML24075A006)
• ML24075A008  + (ML24075A008)
• ML24075A027  + (ML24075A027)
• ML24075A079  + (ML24075A079)
• TSTF-24-02, Technical Specifications Task Force - Transmittal of TSTF-597, Revision 0, Eliminate LCO 3.0.3 Mode 2 Requirement  + (ML24075A080)
• IR 05000352/2024010  + (ML24075A095)
• PMNS20240378, NRC Meeting with Omaha Public Power District to Discuss Submittal of Final Status Surveys for the Decommissioning of Fort Calhoun Station, Unit 1  + (ML24075A099)
• ML24075A100  + (ML24075A100)
• ML24075A102  + (ML24075A102)
• 05000317/LER-2024-001, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed  + (ML24075A103)
• ML24075A114  + (ML24075A114)
• ML24075A115  + (ML24075A115)
• ML24075A116  + (ML24075A116)
• ML24075A117  + (ML24075A117)
• ML24075A118  + (ML24075A118)
• NRC-24-0019, Submittal of 2023 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report  + (ML24075A119)
• ML24075A120  + (ML24075A120)