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 Issue dateTitle
05000237/LER-2016-00215 July 2016Unit 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
ENS 47151High Pressure Coolant Injection System Inoperable Due to Valve Body Leak
ENS 47947Hpci Declared Inoperable
ENS 48009Hpci Declared Inoperable Due to Leakage
IR 05000237/20090046 November 2009IR 05000237-09-004, 05000249-09-004 on 07/01/2009 - 09/30/2009 for Dresden, Units 2 & 3
IR 05000237/201000210 May 2010IR 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 05000237/20110047 November 2011IR 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 05000237/201100525 January 2012IR 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 05000237/20150027 August 2015IR 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
IR 05000237/201600324 October 2016
IR 05000237/201600430 January 2017NRC Integrated Inspection Report 05000237/2016004; 05000249/2016004; 05000237/2016501 and 05000249/2016501
IR 05000237/201700330 October 2017NRC Integrated Inspection Report 05000237/2017003 and 05000249/2017003
IR 05000237/201700422 January 2018NRC Integrated Inspection Report 05000237/2017004; 05000249/2017004; and Emergency Preparedness Annual Inspection Report 05000237/2017501; 05000249/2017501
IR 05000237/20210031 November 2021Integrated Inspection Report 05000237/2021003 and 05000249/2021003
Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants.22 April 1988Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants.
Information Notice 1994-79, Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping23 November 1994Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping
ML0316110031 July 2003Relief Request, CR-25 for Third 10-Year Inservice Inspection Interval
ML03304038230 October 2003IR 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
ML10155056924 July 2009Letter 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.
ML10197038524 August 2009LS-AA-125-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping
ML16230A2376 September 2016Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322)
ML17194B27623 August 1982Forwards 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
ML17261B16414 September 2017Request for Enforcement Discretion for Technical Specification (TS) 3.1.7, Standby Liquid Control (SLC) System.
ML17261B23718 September 2017Notice of Enforcement Discretion for Dresden Nuclear Power Station, Unit 3, NOED 17-3-001
ML19344E14918 August 1980LER 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
ML20063H04827 July 1982SEP Topic III-5.A,High Energy Pipe Breaks Inside Containment, Revised Draft Interim Progress Rept
ML20141C3927 May 1997FOIA Request for Documents Re Current List of Plant Issues Matrix Related to Listed Facilities,Per 5 Usc 552(a)(3) & 10CFR9.23(b)
NRC Generic Letter 1986-013 January 1986NRC Generic Letter 1986-001: Safety Concerns Associated with Pipe Breaks in the BWR Scram System
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 114 June 2016Proposed 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-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 2002Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii) Regarding Control Rod Drive Housing Welds (Relief Request Number CR-25)
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 124 September 2014Proposed 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
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 2016Proposed 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.
SVPLTR 13-0020, Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-0026 June 2013Written Response to Preliminary White Finding from NRC Integrated Inspection Report 2013-002
SVPLTR 20-0014, Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual21 April 2020Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual