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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

• ML030970357  + (Supplement to Fourth-Interval Inservice Testing (IST) Program Plan)
• ML030780296  + (Supplement to Fourth-Interval Inservice Testing Program Plan)
• ML040560540  + (Supplement to Fourth-Interval Inservice Inspection (ISI) Program Plan, Withdrawal of Relief Request PT-1)
• ML040210774  + (Supplement to Fourth-Interval Inservice Inspection (ISI) Program Plan, Submittal of Revised Relief Request ISI-09)
• ML12265A394  + (Supplement to Friends of the Coast & New England Coalitions Motion for Leave to File New Contention Re NextEra Energy Seabrooks Amendment of Its Aging Management Program for Safety-Related Concrete Structures)
• ML20293A423  + (Supplement to Fuel Cycle Program Integrated Schedule October 2020 - MARK-UP)
• ML20105A376  + (Supplement to Fuel Cycle Program Integrated Schedule)
• ML20112F152  + (Supplement to Fuel Cycle Program Integrated Schedule - April 2020)
• ML18346A656  + (Supplement to Fuel Cycle Program Integrated Schedule - Dec 2018)
• ML20293A422  + (Supplement to Fuel Cycle Program Integrated Schedule October 2020)
• ML071030336  + (Supplement to Generic Letter 2003-01, Control Room Habitability)
• NRC 2003-0025, Supplement to Generic Letter 96-06 Resolution  + (Supplement to Generic Letter 96-06 Resolution)
• ML031430498  + (Supplement to Generic Letter 96-06 Resolution)
• ML031120595  + (Supplement to Generic Letter 96-06 Resolution)
• ML25097A174  + (Supplement to Gle Paducah Laser Enrichment Facility (Plef) Environmental Report (Er) Appendix E Subsurface Investigation in Gle Study Area Seasonal Variation)
• RA-20-0088, Supplement to H.B Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal Enclosure Update - Public - Redacted  + (Supplement to H.B Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal Enclosure Update - Public - Redacted)
• RNP-RA/14-0090, Supplement to H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP2) Orginal Submittal Regarding License Amendment Request for Technical Specifications Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feed  + (Supplement to H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP2) Orginal Submittal Regarding License Amendment Request for Technical Specifications Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater)
• RA-20-0177, Supplement to H.B. Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal - Site Actions  + (Supplement to H.B. Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal - Site Actions)
• ML18208A636  + (Supplement to HI-STORM FW Amendment 4 RAIs Responses)
• ML18208A637  + (Supplement to HI-STORM FW Amendment 4 RAIs Responses)
• ML22032A017  + (Supplement to Holtec Decommissioning International, LLC, Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR Part 50, Appendix E Including Site-Specific Calculations)
• LR-N10-0319, Supplement to Hope Creek License Renewal Application Related to the Selective Leaching Program  + (Supplement to Hope Creek License Renewal Application Related to the Selective Leaching Program)
• L-08-288, Supplement to Information Provided in License Renewal Application Amendment No. 23 Regarding Submersible Cable Suitability  + (Supplement to Information Provided in License Renewal Application Amendment No. 23 Regarding Submersible Cable Suitability)
• ML16189A076  + (Supplement to Information Regarding License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System)
• RS-11-070, Supplement to Information Supporting Request for License Amendment Regarding Ultimate Heat Sink  + (Supplement to Information Supporting Request for License Amendment Regarding Ultimate Heat Sink)

• CP-202000269, Supplement to Inservice Inspection (ISI) Program Relief Request  + (Supplement to Inservice Inspection (ISI) Program Relief Request)

• ML071790390  + (Supplement to Inservice Inspection (ISI) Relief Request No. 36 - Proposed Alternative Associated with the Use of Full-Structural Weld Overlays in the Repair of Dissimilar Metal Welds)
• ML071710422  + (Supplement to Inservice Inspection (ISI) Relief Request No. 36 - Proposed Alternative Associated with the Use of Full-Structural Weld Overlays in the Repair of Dissimilar Metal Welds)
• JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 25  + (Supplement to Inservice Inspection Summary Report Cycle 25)
• DCL-05-083, Supplement to Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests  + (Supplement to Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests)
• ML070590333  + (Supplement to Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt-Welds)
• ML23114A141  + (Supplement to Integrated Schedule (October 2022 - May 2023))
• ML20201A014  + (Supplement to Integrated Schedule - July 2020)
• ML21077A088  + (Supplement to Integrated Schedule - March 2021)
• ML24113A246  + (Supplement to Integrated Schedule - May 2024)
• ML23303A176  + (Supplement to Integrated Schedule - November 2023)
• ML21288A148  + (Supplement to Integrated Schedule June - October 2021 (Final))
• ML21161A281  + (Supplement to Integrated Schedule March - June 2021)
• ML20201A013  + (Supplement to Integrated Schedule Markup April-July 2020)
• ML22287A054  + (Supplement to Integrated Schedule May - October 2022)
• ML21082A424  + (Supplement to Integrated Schedule October 2020 - March 2021)
• ML19070A217  + (Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation)
• L-PI-09-008, Supplement to Irradiated Fuel Management Plan and Preliminary/ Decommissioning Cost Estimates for Prairie Island Nuclear Generations Plant (PINGP)  + (Supplement to Irradiated Fuel Management Plan and Preliminary/ Decommissioning Cost Estimates for Prairie Island Nuclear Generations Plant (PINGP))
• L-PI-09-031, Supplement to Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates  + (Supplement to Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates)
• ML25171A113  + (Supplement to January 2025 License Amendment Application Environmental Submittal for Up to 6.5% Enrichment)
• SBK-L-12099, Supplement to LAR 11-04, Changes to the Technical Specifications for New and Spent Fuel Storage  + (Supplement to LAR 11-04, Changes to the Technical Specifications for New and Spent Fuel Storage)
• SBK-L-14184, Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program  + (Supplement to LAR 13-05, LAR 14-01, LAR 14-02 and LAR 14-03 in Response to Issuance of Amendment 141, Risk-Informed Justifications for Relocation of Specific Surveillance Frequency Requirements to Surveillance Frequency Control Program)
• NRC 2017-0052, Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants  + (Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants)
• ML20206M925  + (Supplement to LARs & 1022,for Amends to Licenses NPF-9,NPF-17,NPF-52,respectively & NPF-62,revising List of Ref Documents Contained in TS 5.6.5b Re COLR Requirements)
• LR-N06-0276, Supplement to LCR S05-08: Request for Change to Technical Specifications, Containment Isolation Valves  + (Supplement to LCR S05-08: Request for Change to Technical Specifications, Containment Isolation Valves)
• 05000316/LER-2074-009, Supplement to LER 1974-009Y-00, Abnormal Occurrence During Performance of Protection System Time Response Testing, the Reactor Trip Breakers Were Closed  + (Supplement to LER 1974-009Y-00, Abnormal Occurrence During Performance of Protection System Time Response Testing, the Reactor Trip Breakers Were Closed)