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 Issue dateTitle
IR 05000237/20220028 August 2022Integrated Inspection Report 05000237/2022002; 05000249/2022002 and 07200037/2022002 and Exercise of Enforcement Discretion
IR 05000237/20210047 February 2022Integrated Inspection Report 05000237/2021004 and 05000249/2021004
ML22021B6601 February 2022Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1
ML21277A19316 November 2021Enclosure 2, Draft Conforming License Amendments
ML21179A02721 June 20214 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML21179A02821 June 20214 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems
RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments25 March 2021Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments
IR 05000237/20190028 August 2019Integrated Inspection Report 05000237/2019002; 05000249/2019002; and 07200037/2019001
ML18060A3249 March 2018Relief Request I5R-16 Approval of Alternative to Use the Performance Demonstration Initiative Program for Weld Overlay Inspection Qualifications
IR 05000237/201700422 January 2018NRC Integrated Inspection Report 05000237/2017004; 05000249/2017004; and Emergency Preparedness Annual Inspection Report 05000237/2017501; 05000249/2017501
RS-17-158, Fifth Inservice Inspection Interval Relief Request 15R-167 November 2017Fifth Inservice Inspection Interval Relief Request 15R-16
IR 05000237/201400529 January 2015IR 05000237/2014005; 05000249/2014005 and Preliminary White Finding,October 1, 2014 Through December 31, 2014, Dresden Nuclear Power Station, Units 2 and 3, Integrated Inspection
ML14251A0815 September 2014NRR E-mail Capture - FINAL- Request for Additional Information Regarding Dresden Fourth 10-Year Inservice Inspection Interval - Request for Relief I4R-17
ML14225A18313 August 2014NRR E-mail Capture - Draft Request for Additional Information Regarding Dresden Fourth 10-Year Inservice Inspection Interval - Request for Relief I4R-17
RA-11-087, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-789, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section XI, Divisi10 November 2011Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-789, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section XI, Divisio
ML11202A18129 June 2011Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected Systems
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected Systems29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected Systems
RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements5 October 2007Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
IR 05000237/20060111 February 2007IR 05000237-06-011; 05000249-06-011; 10/01/2006 - 12/31/2006; Dresden, 2 and 3; Fire Protection, Operability Evaluations, and Event Follow-Up
SVPLTR 05-0008, Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report7 March 2005Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report
RS-04-065, Request for Relief from ASME Section XI for Performance of Class 2 & 3 Raw Water Piping Repairs26 April 2004Request for Relief from ASME Section XI for Performance of Class 2 & 3 Raw Water Piping Repairs
SVPLTR 04-0001, Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report9 February 2004Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report
ML0316110031 July 2003Relief Request, CR-25 for Third 10-Year Inservice Inspection Interval
IR 05000237/200201728 January 2003IR 05000237-02-017 & IR 05000249-02-017, on 10/01 - 12/28/2002, Exelon Generation Company. Non-Cited Violations Noted
ML03029009024 January 2003Inservice Inspection (ISI) Summary Report Fall 2002 Inservice Inspection Period
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-02-071, Request for Approval of Quality Assurance Program Changes for Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Nuclear Power Plants9 April 2002Request for Approval of Quality Assurance Program Changes for Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Nuclear Power Plants
ML0204506085 February 2002Inservice Inspection (ISI) Summary Report Fall 2001 Inservice Inspection Period
ML20217D42630 September 1997Informs of Scheduled Visits W/Nuclear Services at Gpu on Nov 14th & Visit at Commonwealth Edison on Dec 3rd & Would Like to Receive Any Info Available.Supporting Documentation Encl
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)
ML20210N4272 December 1996Informs About Drop in Meeting on 961203 for Update on Industry Restructuring & Deregulation,Unicom Strategic Planning & Mixed Oxide Fuel
ML20210N3705 October 1995Forwards Background Briefing Package in Preparation for 951011 Meeting W/Company Executives & Chairmam Jackson
Information Notice 1991-32, Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering15 May 1991Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering
Information Notice 1991-05, Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles30 January 1991Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles
Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head30 April 1990Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head
Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm23 January 1990Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm
ML20248D15713 September 1989Rev 56 to QA Program
Information Notice 1987-64, Conviction for Falsification of Security Training Records22 December 1987Conviction for Falsification of Security Training Records
ML20235H76130 June 1987Rev 45 to CE-1-A, QA Program for Nuclear Generating Stations
ML20151Z7085 March 1987Sanitized Version of Audit on 870224-26 of ASME Class 2 & 3 Valves,Parts & Appurtenances
ML20154A28313 December 1986Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985
ML20153H43426 February 1986Informs That NRC Will Perform Independent Verification Insp During 860331-0411 at Facility Using NDE Van & Contractor Technicians.List of Required Info to Obtain Access to Facility & Weld Data Packages Requested
Information Notice 1985-97, Jail Term for Former Contractor Employee Who Intentionally Falsified Welding Inspection Records, Attachment 1 to NRC Information Notice 1986-05426 December 1985Jail Term for Former Contractor Employee Who Intentionally Falsified Welding Inspection Records, Attachment 1 to NRC Information Notice 1986-054
ML20127F6413 May 1985Responds to NRC Re Violations Noted in Insp Repts 50-373/84-25,50-374/84-32,50-237/84-15,50-249/84-14, 50-254/84-15,50-265/84-13,50-295/84-19 & 50-304/84-20. Corrective Actions Re Commercial Grade Matl Provided
Information Notice 1984-92, Cracking of Flywheels on Cummins Fire Pump Diesel Engines17 December 1984Cracking of Flywheels on Cummins Fire Pump Diesel Engines
ML20024D83428 July 1983LER 83-055/01T-0:on 830719,one 1/8 by 1/16-inch Hole Found on Bellows Seal on Torus to Drywell Vacuum Breaker Line Containing Breakers 2-1601-32A & B.Cavity Filled to Original Thickness & Surface buffed.W/830728 Ltr
ML20027B57020 September 1982Forwards Util 820903 Submittal Responding to NRC Request for Info Re Resolution of Certain Unresolved Safety Issues
ML20084E33127 January 1975Ro:On 741227-28,cracks Discovered in Feedwater Spargers. Caused by Flow Induced Vibration.Predominant Failure Mode Appears to Be Fatigue Cracking.Corrective Actions Include Liquid Penetrant Exam & Sparger Replacement
ML20084F5162 October 1972Submits Results of Investigation Into Flow Reduction on Main Steam Line B.Visual Exam Revealed Weld Discontinuities.Main Steam Line Flow Elements Modified
ML20090D8855 June 1970Supplementary Info to Special Rept of Incident of 700605