Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML04273026023 September 2004Meeting Presentation, Extended Power Uprate (EPU) Vibration Assessment and Vulnerability Review
ML0513602332 May 2005RO Initial Exam - May 2005
ML05161036831 May 2005Initial Submittal of the RO Written Exam for the Quad Cities Initial Examination - May 2005
ML05166021014 June 2005Tech Spec Pages for Amendments 226 and 221 the Deletion of Technical Specification Requirements to Maintain Hydrogen Recombiners and Hydrogen/Oxygen Monitors and Related Surveillance Requirements
ML06073036815 December 2005Attachments 1 Through 4 to Exelon Letter Dated December 15, 2005
ML06095046131 March 2006Tech Spec Page for Amendment 226 Regarding Minimum Critical Power Ratio Safety Limit
ML0711003662 May 2007Technical Specifications, Issuance of Amendment Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit
ML07201017126 July 2007Ro/Sro Initial Examination - Quad Cities June 2007
ML07292041718 October 2007Initial Submittal of the Scenarios for the Quad Cities Initial Examination - June 2007
ML07292042018 October 2007Initial Submittal of the Written Exam for the Quad Cities Initial Examination - June 2007
ML08031007328 February 2008Technical Specifications, Issuance of Amendments Safety Limit Minimum Critical Power Ratio
ML0806704197 March 2008CDBI Findings
ML11196A19210 June 20112011 Quad Cities Nuclear Power Station Initial License Examination Administered Written Examination
ML11305A05419 October 2011Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems
ML11305A05619 October 2011Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 07 - Instrumentation and Controls
ML11305A06119 October 2011Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 10 - Steam and Power Conversion System
ML11305A06819 October 2011Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses
ML11305A13519 October 2011Technical Specification Bases
ML1132027958 March 2012Issuance of Amendment No. 250 and 245, Regarding Technical Specification Change for Minimum Critical Power Safety Limit
ML11326034822 November 2011Request for Technical Specification Change for Safety Limit Minimum Critical Power Ratio
ML15324A43917 December 2015Issuance of Amendments (CAC Nos. MF5471-MF5476)
ML16111A10411 May 2016Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644)
ML16209A21826 July 2016Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML16216A5602 May 20162016 Quad Cities Nuclear Power Station Initial License Examination Proposed Written Examination
ML16216A5742 May 20162016 Quad Cities Nuclear Power Station Administered Written Examination
ML16280A4026 October 2016License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML17138A1233 May 2017Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3
ML17298A33719 October 2017Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML17298A34219 October 2017Revision 14 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
ML17298A34919 October 2017Revision 14 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML17298A36019 October 2017Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis
ML18012A68919 October 2017Revision 14 to Updated Final Safety Analysis Report, Fire Protection Report Vol. 2 Redacted
ML18353A22928 January 2019Issuance of Amendment Nos. 273 and 268 Regarding Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control
ML19239A03523 August 2019NRC-2019-000303 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed
ML19257A72810 December 1979LER 79-038/01T-0:on 791128,scram & ECCS Initiation Setpoints Set Lower than Required by Tech Specs.Caused by Initial Instrument Ref Leg Calculations Based on Temp of 135 F. Indicating Switches Recalibr
ML19301A3394 December 2019Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, the Minimum Critical Power Ration Safety Limits
ML19341A0211 January 1981Monthly Operating Repts for Dec 1980
ML20015A42915 January 2020UFSAR Revision 15 Chapter 6 Engineered Safety Features - Redacted
ML20015A43615 January 2020Revision 24 to Fire Protection Report, Volume 2 - Redacted
ML20059K73514 January 1994Application for Emergency Amend to License DPR-30 for NRC Review & Approval of Two USQs Associated W/Interim Mod on Quad-Cities Station Unit 2,to Resolve Concerns Described in NRC Bulletin 93-003
ML20062D36930 October 1978Monthly Operating Rept for Oct 1978
ML20063H32031 January 1994Monthly Operating Repts for Jan 1994 for Quad Cities Nuclear Power Station Units 1 & 2
ML20072D72231 July 1994Monthly Operating Repts for July 1994 for Quad-Cities Nuclear Station Units 1 & 2
ML20079F99230 September 1991Proposed Tech Spec 3.8/4.8 Re Radioactive Effluents & 3.10/4.10 Re Refueling
ML20081L16327 June 1991Application for Amends to Licenses DPR-29 & DPR-30,changing Tech Specs to Reflect Util Efforts to Upgrade Existing TS 1.2/2.1 Re Fuel Cladding Integrity & 1.2/2.2 Re RCS
ML20081L16827 June 1991Proposed Tech Specs 1.1/2.1 Re Fuel Cladding Integrity & 1.2/2.2 Re RCS
ML20084K81018 June 1974Ao:On 740610,feedwater Low Flow Regulating Valve AO-2-643 Failed.Some Radioactive Water May Have Escaped to Outside Environ.Caused by Fracture at Junction of Valve Body & Reduced Wall Thickness.New Valve Installed
ML20084U91710 March 1975AO 50-265/74-32:on 741231,MSIV Leak Rate Testing Revealed Excessive Leakage on Steam Lines A,B & C.Caused by Warpage Due to Washing of Seat Valve
ML20087D86110 January 1992Submits Reactor Reference Leg Mod Schedule Update for Installation of New Containment Penetrations,Condensing Chambers & Instrument Lines,Per Re Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs
ML20087H8652 May 1995Proposed Tech Specs Re TS Upgrade Program Section 3/4.10