Pre-submittal aka pre-application is a project stage when a license amendment request plan is presented and discussed with the NRC prior to submittal.
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ML24313A105 | 13 November 2024 | Hatch | November 13, 2024, Hatch Pre-Submittal Public Meeting Slides (Southern Co.) | ML24311A033 | 7 November 2024 | Sequoyah | TVA Pre-Submittal Meeting Presentation on License Amendment Request to Revise SR 3.4.14.1 Reactor Coolant System Pressure Isolation Valves Leakage Testing Frequency on November 7, 2024 | ML24311A052 | 7 November 2024 | | Presentation - Framatome November 7, 2024, EMF-93-177, Revision 1, Supplement 3, Atrium Boiling Water Reactor (BWR) Enhanced Accident Model (A-Beam) Topical Report Pre-Submittal Meeting - Open Session | PMNS20241383, Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 2 | 7 November 2024 | Watts Bar | Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 2 | PMNS20241406, Pre-Submittal Meeting Regarding a Proposed License Amendment Request to Revise Various Technical Specification Shutdown Actions Mode Change Restrictions | 7 November 2024 | Vogtle | Pre-Submittal Meeting Regarding a Proposed License Amendment Request to Revise Various Technical Specification Shutdown Actions Mode Change Restrictions | PMNS20241350, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Unit 2, Fitness for Duty Exemption | 7 November 2024 | Sequoyah | Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Unit 2, Fitness for Duty Exemption | ML24311A157 | 6 November 2024 | Wolf Creek | Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors | PMNS20241312, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specification 3.4.14 Related to Reactor Coolant System Pressure Isolation Valve Leakage | 6 November 2024 | Sequoyah | Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant License Amendment Request to Revise Technical Specification 3.4.14 Related to Reactor Coolant System Pressure Isolation Valve Leakage | ML24310A067 | 5 November 2024 | Calvert Cliffs Dresden Peach Bottom Nine Mile Point Byron Braidwood Limerick Ginna Clinton Quad Cities FitzPatrick LaSalle | Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization | ML24305A200 | 4 November 2024 | Saint Lucie | Pre-Submittal Meeting - St. Lucie, Unit 1 - Criticality Analysis for Transition to 24-Month Fuel Cycle (L-2023-LRM-0122) |
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