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| Issue date | Title | |
|---|---|---|
| IR 05000237/2021003 | 1 November 2021 | Integrated Inspection Report 05000237/2021003 and 05000249/2021003 |
| SVPLTR 20-0014, Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual | 21 April 2020 | Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual |
| IR 05000237/2017004 | 22 January 2018 | NRC Integrated Inspection Report 05000237/2017004; 05000249/2017004; and Emergency Preparedness Annual Inspection Report 05000237/2017501; 05000249/2017501 |
| IR 05000237/2017003 | 30 October 2017 | NRC Integrated Inspection Report 05000237/2017003 and 05000249/2017003 |
| ML17261B237 | 18 September 2017 | Notice of Enforcement Discretion for Dresden Nuclear Power Station, Unit 3, NOED 17-3-001 |
| ML17261B164 | 14 September 2017 | Request for Enforcement Discretion for Technical Specification (TS) 3.1.7, Standby Liquid Control (SLC) System. |
| IR 05000237/2016004 | 30 January 2017 | NRC Integrated Inspection Report 05000237/2016004; 05000249/2016004; 05000237/2016501 and 05000249/2016501 |
| IR 05000237/2016003 | 24 October 2016 | |
| ML16230A237 | 6 September 2016 | Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) |
| 05000237/LER-2016-002 | 15 July 2016 | Unit 2 HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability LER 16-002-00 for Dresden Nuclear Power Station, Unit 2 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability |
| RA-16-059, Proposed Alternative to Utilize Code Case N5134, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 14 June 2016 | Proposed Alternative to Utilize Code Case N5134, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 |
| RS-16-041, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1. | 28 January 2016 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1. |
| IR 05000237/2015002 | 7 August 2015 | IR 05000237/2015002, 05000249/2015002 & 07200037/2015001; 04/01/2015 - 06/30/2015; Dresden Nuclear Power Station, Units 2 and 3; Integrated; Maintenance Risk Assessments and Emergent Work Control, Surveillance Testing, Follow-Up of Events |
| RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 24 September 2014 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 |
| ML13260A585 | 30 September 2013 | Cover Letter -Safety Evaluation in Support of Request for Relief Associated with the Fifth 10-Year Interval Inservice Inspection Program (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc |
| SVPLTR 13-0020, Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002 | 6 June 2013 | Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002 |
| IR 05000237/2011005 | 25 January 2012 | IR 05000237-11-005, 05000249-11-005, on 10/01/2011 - 12/31/2011, Dresden Nuclear Power Station, Units 2 & 3, Followup of Events and Notices of Enforcement Discretion |
| IR 05000237/2011004 | 7 November 2011 | IR 05000237-11-004 & 05000249-11-004, 07/01/2011 - 09/30/2011, Dresden Nuclear Power Station, Units 2 & 3, Adverse Weather, Flooding, Plant Modifications, Post-Maintenance Testing |
| IR 05000237/2010002 | 10 May 2010 | IR 05000237-10-002 & 05000249-10 002, on 01/01/2010 - 03/31/2010, Dresden, Units 2 & 3; Surveillance Testing, Post-Maintenance Testing, Radiation Monitoring Instrumentation, Identification and Resolution of Problems, and Follow Up of Events |
| IR 05000237/2009004 | 6 November 2009 | IR 05000237-09-004, 05000249-09-004 on 07/01/2009 - 09/30/2009 for Dresden, Units 2 & 3 |
| ML101970385 | 24 August 2009 | LS-AA-125-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping |
| ML101550569 | 24 July 2009 | Letter LS-AA-1 25-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping for Dresden Units 2 and 3. |
| ML033040382 | 30 October 2003 | IR 05000237-03-007 and IR 05000249-03-007; on 07/01/2003 - 09/30/2003, Dresden Nuclear Power Station, Units 2 and 3; Fire Protection, Event Followup, Other Activities |
| ML031611003 | 1 July 2003 | Relief Request, CR-25 for Third 10-Year Inservice Inspection Interval |
| RS-02-187, Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii) Regarding Control Rod Drive Housing Welds (Relief Request Number CR-25) | 25 October 2002 | Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii) Regarding Control Rod Drive Housing Welds (Relief Request Number CR-25) |
| ML20141C392 | 7 May 1997 | FOIA Request for Documents Re Current List of Plant Issues Matrix Related to Listed Facilities,Per 5 Usc 552(a)(3) & 10CFR9.23(b) |
| Information Notice 1994-79, Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping | 23 November 1994 | Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping |
| Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. | 22 April 1988 | Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. |
| NRC Generic Letter 1986-01 | 3 January 1986 | NRC Generic Letter 1986-001: Safety Concerns Associated with Pipe Breaks in the BWR Scram System |
| ML17194B276 | 23 August 1982 | Forwards Target Technology,Ltd Revised Draft Interim Progress Rept, SEP Topic III-5.A,High Energy Pipe Breaks Inside Containment, Clarifying Five Items Identified in NRC Draft Evaluation Requiring Resolution |
| ML20063H048 | 27 July 1982 | SEP Topic III-5.A,High Energy Pipe Breaks Inside Containment, Revised Draft Interim Progress Rept |
| ML19344E149 | 18 August 1980 | LER 80-033/03L-0:on 800724,during Normal operations,1/4-inch through-wall Leak Discovered in 3A Component Cooling Svc Water Pump Casing.Caused by Casting Hole on Bottom of Casing.Pump Removed & Hole Plugged |