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Issue date | Title | |
---|---|---|
ML042730260 | 23 September 2004 | Meeting Presentation, Extended Power Uprate (EPU) Vibration Assessment and Vulnerability Review |
ML051360233 | 2 May 2005 | RO Initial Exam - May 2005 |
ML051610368 | 31 May 2005 | Initial Submittal of the RO Written Exam for the Quad Cities Initial Examination - May 2005 |
ML051660210 | 14 June 2005 | Tech 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 |
ML060730368 | 15 December 2005 | Attachments 1 Through 4 to Exelon Letter Dated December 15, 2005 |
ML060950461 | 31 March 2006 | Tech Spec Page for Amendment 226 Regarding Minimum Critical Power Ratio Safety Limit |
ML071100366 | 2 May 2007 | Technical Specifications, Issuance of Amendment Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit |
ML072010171 | 26 July 2007 | Ro/Sro Initial Examination - Quad Cities June 2007 |
ML072920417 | 18 October 2007 | Initial Submittal of the Scenarios for the Quad Cities Initial Examination - June 2007 |
ML072920420 | 18 October 2007 | Initial Submittal of the Written Exam for the Quad Cities Initial Examination - June 2007 |
ML080310073 | 28 February 2008 | Technical Specifications, Issuance of Amendments Safety Limit Minimum Critical Power Ratio |
ML080670419 | 7 March 2008 | CDBI Findings |
ML11196A192 | 10 June 2011 | 2011 Quad Cities Nuclear Power Station Initial License Examination Administered Written Examination |
ML11305A054 | 19 October 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems |
ML11305A056 | 19 October 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 07 - Instrumentation and Controls |
ML11305A061 | 19 October 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 10 - Steam and Power Conversion System |
ML11305A068 | 19 October 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses |
ML11305A135 | 19 October 2011 | Technical Specification Bases |
ML113202795 | 8 March 2012 | Issuance of Amendment No. 250 and 245, Regarding Technical Specification Change for Minimum Critical Power Safety Limit |
ML113260348 | 22 November 2011 | Request for Technical Specification Change for Safety Limit Minimum Critical Power Ratio |
ML15324A439 | 17 December 2015 | Issuance of Amendments (CAC Nos. MF5471-MF5476) |
ML16111A104 | 11 May 2016 | Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) |
ML16209A218 | 26 July 2016 | Application 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. |
ML16216A560 | 2 May 2016 | 2016 Quad Cities Nuclear Power Station Initial License Examination Proposed Written Examination |
ML16216A574 | 2 May 2016 | 2016 Quad Cities Nuclear Power Station Administered Written Examination |
ML16280A402 | 6 October 2016 | License 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. |
ML17138A123 | 3 May 2017 | Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3 |
ML17298A337 | 19 October 2017 | Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems |
ML17298A342 | 19 October 2017 | Revision 14 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML17298A349 | 19 October 2017 | Revision 14 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System |
ML17298A360 | 19 October 2017 | Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis |
ML18012A689 | 19 October 2017 | Revision 14 to Updated Final Safety Analysis Report, Fire Protection Report Vol. 2 Redacted |
ML18353A229 | 28 January 2019 | Issuance of Amendment Nos. 273 and 268 Regarding Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control |
ML19239A035 | 23 August 2019 | NRC-2019-000303 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed |
ML19257A728 | 10 December 1979 | LER 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 |
ML19301A339 | 4 December 2019 | Issuance of Amendments to Revise Technical Specification 2.1.1, Reactor Core Safety Limits, the Minimum Critical Power Ration Safety Limits |
ML19341A021 | 1 January 1981 | Monthly Operating Repts for Dec 1980 |
ML20015A429 | 15 January 2020 | UFSAR Revision 15 Chapter 6 Engineered Safety Features - Redacted |
ML20015A436 | 15 January 2020 | Revision 24 to Fire Protection Report, Volume 2 - Redacted |
ML20059K735 | 14 January 1994 | Application 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 |
ML20062D369 | 30 October 1978 | Monthly Operating Rept for Oct 1978 |
ML20063H320 | 31 January 1994 | Monthly Operating Repts for Jan 1994 for Quad Cities Nuclear Power Station Units 1 & 2 |
ML20072D722 | 31 July 1994 | Monthly Operating Repts for July 1994 for Quad-Cities Nuclear Station Units 1 & 2 |
ML20079F992 | 30 September 1991 | Proposed Tech Spec 3.8/4.8 Re Radioactive Effluents & 3.10/4.10 Re Refueling |
ML20081L163 | 27 June 1991 | Application 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 |
ML20081L168 | 27 June 1991 | Proposed Tech Specs 1.1/2.1 Re Fuel Cladding Integrity & 1.2/2.2 Re RCS |
ML20084K810 | 18 June 1974 | Ao: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 |
ML20084U917 | 10 March 1975 | AO 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 |
ML20087D861 | 10 January 1992 | Submits 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 |
ML20087H865 | 2 May 1995 | Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 |