Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML23132A204 | 12 May 2023 | Annual Radioactive Effluent Release Report | Annual Radioactive Effluent Release Report Process Control Program |
SVP-23-022, Correction/Errata for the 2022 Annual Radioactive Effluent Release Report | 12 May 2023 | Correction/Errata for the 2022 Annual Radioactive Effluent Release Report | Annual Radioactive Effluent Release Report Process Control Program |
SVPLTR 23-0004, Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities | 10 February 2023 | Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities | VT-2 Through Wall Leak |
ML20280A248 | 7 October 2020 | Summary of September 22, 2020, Presubmittal Meeting Between the NRC and Exelon Generation Company LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Units 1 and 2 and Dresden, Units 2 and 3 | |
ML17238A122 | 26 August 2017 | Transmittal of Previously Omitted Proposed Technical Specification Page 3.1-2, and Figures 2.1.1, 3.3.1, 3.3.2, 3.5.1, 3.6.1 | |
ML16056A139 | 11 March 2016 | Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports | |
ML15238B691 | 4 September 2015 | Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation | FLEX Fukushima Dai-Ichi |
ML15239B215 | 4 September 2015 | Master Report - Tables 1 and 2 | |
RS-14-297, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. | 26 December 2014 | Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. | Ultimate heat sink Probabilistic Risk Assessment Squib FLEX Fukushima Dai-Ichi Seismically rugged Earthquake Power-Operated Valves |
ML14307B707 | 10 December 2014 | Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T | Probabilistic Risk Assessment Fukushima Dai-Ichi |
RA-13-081, Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term. | 16 September 2013 | Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term. | Fukushima Dai-Ichi Foreign Material Exclusion |
RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites | 12 September 2013 | Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites | Fukushima Dai-Ichi Earthquake |
ML12348A265 | 27 November 2012 | Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Fukushima Dai-Ichi |
ML12012A194 | 11 January 2012 | SAMG-1 Primary Containment Flooding | |
ML12012A195 | 11 January 2012 | SAMG-2 RPV, Containment, and Radioactivity Release Control | |
NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan | 23 July 2010 | Re-Submittal of the Exelon Cyber Security Plan | Cyber Security Incorporated by reference |
ML072820307 | 11 October 2007 | Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists | |
ML070930466 | 24 May 2007 | NRC Receipt of Quad Cities Nuclear Power Station Units 1 & 2, Response to Generic Letter 2003-01, Control Room Habitability (TAC No. MB9845 and MB9846) | |
ML063040661 | 30 October 2006 | IR Dresden 2006-010 Attachment 3 | Grab sample |
RS-06-156, Response to Request for Additional Information Related to Extended Power Uprate Operation Commitments | 17 October 2006 | Response to Request for Additional Information Related to Extended Power Uprate Operation Commitments | Foreign Material Exclusion |
ML061720095 | 16 June 2006 | Orise - Interim Letter Report for Analytical Results for Four of Eight Water Samples, Batch Four, from the Vicinity of the Dresden Generating Station, Dresden, Illinois (Inspection Report No. 050-00237/2006-007) (Rfta No. 06-001) | |
RS-05-123, Commitments and Plans Related to Extended Power Uprate Operation | 23 September 2005 | Commitments and Plans Related to Extended Power Uprate Operation | Finite Element Analysis |
ML032340717 | 3 June 2002 | Outline Submittal for the Dresden Initial Exam - June 2002 | |
ML17252B627 | 25 May 1979 | Seismic Evaluation Effort and Analyses Recommendations | |
ML17252B625 | 25 May 1979 | Seismic Evaluation Effort and Analyses Recommendations | |
ML17252B047 | 30 November 1977 | NEDO-24074 General Electric Boiling Water Reactor Reload-5 Licensing Submittal for Dresden Nuclear Power Station Unit 3. | Shutdown Margin Stroke time Abnormal operational transient Fuel cladding |
ML18227D146 | 26 February 1976 | Quad-Cities Units 1 & 2 - Submits Table 2, Revised as Supplement C to Quad-Cities Special Report, Which Indicates Latest Core Wide Metal to Water Reaction Percentage of .18 | |
ML17252A452 | 14 August 1975 | Report of Abnormal Occurrences Per Section 6.6.A of the Technical Specifications Primary Containment Local Leak-Rate Testing (1975 Refueling Outage) | |
ML17252B041 | 28 July 1975 | Summary Report of the Investigatory Work Performed on Dresden 3 Control Rod Drive Collet Housing Cracks | |
ML17252B051 | 31 August 1974 | Summary Technical Report of Primary Containment Leak Rate Testing | |
ML17252A903 | 23 May 1974 | Letter Reporting a Condition Relating to the Operation of Dresden Nuclear Power Station Unit 3 on 05/15/1974 - Violation of Main Steam Line Area Temperature Detectors | |
ML17252B182 | 29 March 1974 | Report No. 29, Supplement B Transient Analysis for Dresden-3 Cycle 3 and Quad-Cities-1 Cycle 2. | Abnormal operational transient Feedwater Controller Failure |
ML17252A927 | 25 January 1974 | Letter Reporting a 01/16/1974 Occurrence Relating to the Failure of Relief Valve 3-203-3A to Operate - Dresden Unit 3 | |
ML17252B181 | 20 June 1973 | Special Report No. 29 Transient Analyses for Cycle 2 Using Current Methods. | Feedwater Controller Failure Fast acting solenoid valve |
ML17252B009 | 8 December 1972 | Letter Reporting a 11/11/1972 Condition Relating to the Discovery of the Main Steam Isolation Valve 3-203B-1B to Have a Closure Time Outside the Technical Specification Limit - Dresden Unit 3 | |
ML17252B180 | 22 February 1972 | Supplement to Special Report No. 14, Containment Flammability Control in a Boiling Water Reactor. | |
ML17252B172 | 24 May 1971 | Special Report No. 14, Hydrogen Flammability Control System in a Boiling Water Reactor. | Grab sample Fuel cladding Backfit |
ML17252B052 | 16 October 1970 | Welding Procedure Specification No. P8-P1-GTA-F5-2G |