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| Issue date | Title | Topic | |
|---|---|---|---|
| ML073410146 | 20 December 2007 | Request for Withholding Information from Public Disclosure - Cycle 20 SLMCPR | |
| ML073400600 | 19 December 2007 | Letter to C. Pardee Correction of Administrative Error in Amendment - the Consistency of TSs to Exelon Generation Company Quality Assurance TR (Tacs. MD3937 Thru MD3940 and MD3943 Thru MD3948) | |
| ML073540330 | 19 December 2007 | Quad - Inspection Plan 1/1/08 - 12/31/08 | |
| ML073540049 | 19 December 2007 | Letter to C. Pardee Correction of Administrative Error in Amendment - the Consistency of TSs to Exelon Generation Company Quality Assurance TR (Tac. MD3937 Thru MD3940 and MD3943 Thru MD3948). - Rplacement Pages | Safeguards Contingency Plan Fire Protection Program |
| RS-07-167, Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and Divom Correlation | 17 December 2007 | Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and Divom Correlation | Minimum Critical Power Ratio |
| RS-07-156, Company, Llc/Amergen Energy Company, LLC Response to the Request for Additional Information (RAI) Regarding Resolution of NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident. | 7 December 2007 | Company, Llc/Amergen Energy Company, LLC Response to the Request for Additional Information (RAI) Regarding Resolution of NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident. | |
| ML072990422 | 29 November 2007 | Fleet, Request for Additional Information Use of the Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of the ASME Code Requirements | VT-2 Dissimilar Metal Weld |
| TAC:MD7374 | 20 November 2007 | ||
| RS-07-157, Request for Technical Specification Change for Minimum Power Ratio Safety Limit | 20 November 2007 | Request for Technical Specification Change for Minimum Power Ratio Safety Limit | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Fuel cladding |
| ML073130052 | 20 November 2007 | Relief from 5-Year Test Interval for Main Steam Safety Valves | |
| ML073331094 | 19 November 2007 | Tech Specs for Amendments to Provide Consistency with Quality Assurance Topical Report | Safe Shutdown Safeguards Contingency Plan Fire Protection Program |
| ML072250411 | 19 November 2007 | License Amendments to Provide Consistency with Quality Assurance Topical Report | |
| TAC:MD3938 | 19 November 2007 | ||
| TAC:MD3937 | 19 November 2007 | ||
| ML073170213 | 9 November 2007 | Proposed Examination Cover Letter and Checklists for the Quad Cities Nuclear Power Station Initial Examination June 2007 | |
| ML073170238 | 9 November 2007 | Licensee/Nrc Comments to the Proposed Written Examination, ES-401-9 for the Quad Cities Nuclear Power Station Initial Exam - June 2007 | |
| ML073170287 | 9 November 2007 | Miscellaneous Correspondence for the Quad Cities Nuclear Power Station Initial Examination June 2007 | |
| ML073170229 | 9 November 2007 | Licensee/Nrc Comments to the Proposed Operating Test for the Quad Cities Nuclear Power Station Initial Exam - June 2007 | Safe Shutdown |
| ML073170204 | 9 November 2007 | Examination Outline Submittal for the Quad Cities Nuclear Power Station Initial Examination June 2007 | Safe Shutdown |
| ML073200086 | 9 November 2007 | Notification of Potential Part 21 Report Conval Valves Weld Qualifications | |
| ML073170307 | 9 November 2007 | Various Checklists for the Quad Cities Nuclear Power Station Initial Examination June 2007 | Job Performance Measure |
| ML073170299 | 9 November 2007 | Facility Post - Examination Comments for the Quad Cities Nuclear Power Station Initial Examination June 2007 | |
| ML072710011 | 7 November 2007 | Request for Additional Information Related to Relief Request (RV-30E) | |
| ML072920307 | 6 November 2007 | RAI | |
| ML073100099 | 6 November 2007 | Federal Emergency Management Agency, Final Report for September 28, 2007 Medical Service Drill of the Offsite Radiological Emergency Response Plans Site-Specific to the Quad Cities Nuclear Power Station | |
| SVP-07-069, Core Operating Limits Report, Cycle 20 (Revision 2) | 5 November 2007 | Core Operating Limits Report, Cycle 20 (Revision 2) | Safety Limit Minimum Critical Power Ratio MELLLA |
| ML072290170 | 1 November 2007 | Issuance of Amendments to Increase the Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment | Stroke time Anticipated operational occurrence Feedwater Controller Failure Safeguards Contingency Plan Fire Protection Program |
| ML073110102 | 1 November 2007 | Issuance of Amendments to Increase the Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment - Tech. Spec. Pages | |
| IR 05000254/2007004 | 31 October 2007 | IR 05000254-07-004 & IR 05000265-07-004; Exelon Nuclear; on 07/01/2007 - 09/30/2007; Quad Cities Nuclear Power Station, Units 1 & 2; Refueling and Outage Activities; Event Followup; and Other Activities | Safe Shutdown Packing leak Ultimate heat sink Fire Barrier Internal Flooding Temporary Modification Condition Adverse to Quality Significance Determination Process Annual Radioactive Effluent Release Report Foreign Material Exclusion Scram Discharge Volume Process Control Program Maintenance Rule Program Hardened vent Weak link |
| RS-07-146, Response to Request for Additional Information Related to Relief Request RV-30E | 30 October 2007 | Response to Request for Additional Information Related to Relief Request RV-30E | |
| ML073520539 | 28 October 2007 | LTR-07-0819 - Ltr. Tom Gurdziel, Concerns New Generation of Nuclear Plants | |
| ML073240024 | 25 October 2007 | Examples of Max Thermal Power License Conditions | |
| ML072840198 | 19 October 2007 | SDP Notebook Transmittal Letter (Public Version) | Significance Determination Process |
| ML072820157 | 19 October 2007 | Request for Withholding Information from Public Disclosure Regarding Backup Stability Protection Methodology | |
| ML072920319 | 18 October 2007 | Initial Submittal of the Scenarios for the Quad Cities Intial Examination - June 2007 | Half scram Post Accident Monitoring Power change |
| ML072920286 | 18 October 2007 | Final As-Administered Scenarios for the Quad Cities Initial Examination - June 2007 | Half scram Scram Discharge Volume Overtravel |
| ML072920420 | 18 October 2007 | Initial Submittal of the Written Exam for the Quad Cities Initial Examination - June 2007 | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Half scram Feedwater Controller Failure Containment Hardened Vent |
| ML072920417 | 18 October 2007 | Initial Submittal of the Scenarios for the Quad Cities Initial Examination - June 2007 | Reactor Vessel Water Level Job Performance Measure |
| ML072920394 | 18 October 2007 | Initial Submittal of the In-Plant Jpms for the Quad Cities Initial Examination - June 2007 | Job Performance Measure |
| ML072920379 | 18 October 2007 | Initial Submittal of the Administrative Jpms for the Quad Cities Initial Examination - June 2007 | Safe Shutdown Job Performance Measure |
| ML072920227 | 18 October 2007 | Final As-Administered Simulator Jpms for the Quad Cities Initial Examination - June 2007 | Stroke time Job Performance Measure |
| ML072920210 | 18 October 2007 | Final As-Administered In-Plant Jpms for the Quad Cities Initial Examination - June 2007 | Job Performance Measure |
| ML072910705 | 18 October 2007 | Final As-Administered Administrative Jpms for the Quad Cities Initial Examination - June 2007 | Safe Shutdown Job Performance Measure |
| IR 05000254/2007404 | 18 October 2007 | IR 05000254-07-404, (Drs), IR 05000265-07-404, (Drs), 09/17/2007 - 09/21/2007, Quad Cities Nuclear Power Station, Routine Security Baseline Inspection - Cover Letter | |
| ML072890262 | 16 October 2007 | PNO-III-08-011:Exelon Nuclear Generating Co, Tritium Leakage | |
| ML072820307 | 11 October 2007 | Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists | |
| IR 05000254/2007008 | 10 October 2007 | IR 05000254-07-008(DRS); 05000265-07-008(DRS); on 08/20/2007 Through 09/07/2007; Quad Cities Nuclear Power Station, Units 1 and 2; Evaluation of Changes, Tests, or Experiments (10 CFR 50.59) and Permanent Plant Modifications | Stroke time Functionality Assessment Significance Determination Process Operability Determination |
| RS-07-117, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process | 9 October 2007 | Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process | Safe Shutdown Ultimate heat sink Stroke time Incorporated by reference Battery sizing Power Operated Valves Recently irradiated fuel Offsite Circuit |
| 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 Requirements | 5 October 2007 | 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 Requirements | Nondestructive Examination VT-2 EVT-1 Liquid penetrant |
| SVP-07-060, Regulatory Commitment Change Summary Report | 28 September 2007 | Regulatory Commitment Change Summary Report |