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Issue date | Title | Topic | |
---|---|---|---|
IR 05000254/2007007 | 30 March 2007 | IR 05000254-07-007; 2/20/2007 - 2/23/2007; Quad Cities Nuclear Plant Unit 1; Supplemental Inspection; Inspection Procedure 95001, Inspection for One or Two White Inputs in a Strategic Performance Area. | Power Uprate |
ML070930556 | 30 March 2007 | Submittal of Midamerican Energy Company'S 2006 Decommissioning Funding Status Report Pursuant to 10 CFR 50.75(f)(1) | |
ML070640415 | 27 March 2007 | Final Response to Quad Cities Nuclear Power Station - Task Interface Agreement (TIA) 2006-005 Appendix R Disputed Violations | Safe Shutdown Exemption Request Fire Protection Program |
ML070810013 | 22 March 2007 | Morning Report 3-2007-0006 - Leadership Changes at Exelon Nuclear | |
ML070820012 | 22 March 2007 | Extended Power Uprate (EPU) Meeting, Handouts from March 22, 2007, Meeting | |
ML071660102 | 20 March 2007 | Slides to Counterparts Meeting with Exelon to Discuss Current and Planned Licensing Activities and Process - Correction | Ultimate heat sink Enforcement Discretion |
ML070790373 | 19 March 2007 | End of Cycle Plant Performance Assessment Letter | |
ML070790377 | 19 March 2007 | Notice of Meeting with Exelon Generation Company, LLC, Quad Cities End of Cycle Plant Performance Assessment | |
ML070670047 | 19 March 2007 | RAI Cycle 20 Minimum Critical Power Ratio Safety Limit | |
ML070750355 | 14 March 2007 | Notification of NRC Inspection and Request for Information 03/14/2007 | Nondestructive Examination VT-2 |
RS-07-039, Request for Safety Evaluation Revision Regarding Backup Stability Protection Methodology | 9 March 2007 | Request for Safety Evaluation Revision Regarding Backup Stability Protection Methodology | |
ML070640533 | 8 March 2007 | Notice of Meeting with Exelon to Discuss the Results and Conclusions of Evaluations and Plant Modifications Performed to Support Extended Power Uprate (EPU) Operation of Quad Cities Nuclear Power Plant, Units 1 and 2 | |
ML071370309 | 7 March 2007 | Velan, Inc., Piston Check Cv Information | |
ML070640584 | 7 March 2007 | Branch Chief Reassignment Letter for Braidwood, Units 1 and 2; Byron, Unit 1 and 2; Clinton, Unit 1; Dresden, Units 2 and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 2; Davis-Besse, Unit 1 and Perry, Unit 1 | |
IR 05000254/2007001 | 2 March 2007 | EOC Annual Assessment Letter (Report 05000254-07-001; 05000265-07-001) | Power Uprate |
ML072740226 | 27 February 2007 | E-mail from M. King, NRR to J. Thorp, NRR on Region 1 and 3 Morning Call Plant Status Notes for Tuesday, 2/27/07 | Mission time Downpower |
ML070600391 | 27 February 2007 | Revised Notice of Meeting with Exelon Generation Co., LLC to Discuss Licensing Issues and Schedule of Upcoming Licensing Activities with the Exelon Fleet of Nuclear Power Plants (Braidwood, Units 1 and 2, Byron, Unit Nos. 1 and 2; Clinton.. | |
SVP-07-013, Core Operating Limits Reports Cycle 19 (Revision 2) | 27 February 2007 | Core Operating Limits Reports Cycle 19 (Revision 2) | Safety Limit Minimum Critical Power Ratio MELLLA |
RS-07-029, Nuclear/Amergen Energy Company, LLC, Fitness for Duty Performance Data Reports - Second Period - 2006 | 22 February 2007 | Nuclear/Amergen Energy Company, LLC, Fitness for Duty Performance Data Reports - Second Period - 2006 | Fitness for Duty |
ML070510139 | 16 February 2007 | 2007 Emergency Preparedness and Incident Response Public Meeting: Status of the EP Threat Based Project, 2/16/07 | B.5.b Mitigating Strategies |
ML070360540 | 15 February 2007 | Forthcoming Meeting with Exelon Generation Company to Discuss Licensing Activities | |
TAC:MD4298 | 7 February 2007 | ||
RS-07-023, Response to Request for Additional Information Regarding Quad Cities Nuclear Power Station, Units 1 & 2, Response to Generic Letter 2003-01, Control Room Habitability. | 7 February 2007 | Response to Request for Additional Information Regarding Quad Cities Nuclear Power Station, Units 1 & 2, Response to Generic Letter 2003-01, Control Room Habitability. | |
IR 05000254/2006007 | 31 January 2007 | IR 05000254-06-007, 05000265-06-007, 05000254-06-016, 05000265-06-016, on 10/01/2006 - 12/31/2006, Quad Cities Nuclear Power Station, Units 1 & 2; Problem Identification and Resolution and Event Followup | High Radiation Area Ultimate heat sink Offsite Dose Calculation Manual Fire Barrier Enforcement Discretion Temporary Modification Locked High Radiation Area Significance Determination Process Job Performance Measure Operability Determination Frazil ice Through-Wall Leak Through Wall Leak Through-Wall Leakage Overexposure |
RS-07-002, Egc/Amergen Response to the Request for Additional Information Regarding Resolution of NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. | 31 January 2007 | Egc/Amergen Response to the Request for Additional Information Regarding Resolution of NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. | High winds Anticipated operational occurrence Probabilistic Risk Assessment |
LR-N07-0034, C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. | 31 January 2007 | C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. | Flow Induced Vibration |
ML070370410 | 30 January 2007 | Exam Confirmation | |
IR 05000254/2006017 | 29 January 2007 | IR 05000254-06-017, 05000265-06-017; 11/27/2006 - 12/15/2006; Quad Cities Nuclear Power Station, Units 1 & 2; Identification and Resolution of Problems | Safe Shutdown Packing leak Enforcement Discretion Significance Determination Process Foreign Material Exclusion Operability Determination Through-Wall Leak Through Wall Leak Power Uprate |
TAC:MB9845 | 25 January 2007 | ||
ML070230359 | 25 January 2007 | RAI, Generic Letter 2003-01, Control Room Habitability, MB9845 and MB9846 | |
RS-07-007, Additional Information Supporting Request for License Amendment to Increase Main Steam Safety Valve Life Setpoint Tolerance and Standby Liquid Control System Enrichment | 24 January 2007 | Additional Information Supporting Request for License Amendment to Increase Main Steam Safety Valve Life Setpoint Tolerance and Standby Liquid Control System Enrichment | Incorporated by reference |
TAC:MD4044 | 24 January 2007 | ||
TAC:MD3689 | 24 January 2007 | ||
SVP-07-004, Core Operating Limits Reports for Plant Cycle 19 (Revision 3) | 23 January 2007 | Core Operating Limits Reports for Plant Cycle 19 (Revision 3) | Safety Limit Minimum Critical Power Ratio |
TAC:MD1181 | 23 January 2007 | ||
ML063620486 | 23 January 2007 | Final Response to Quad Cities Nuclear Power Station - Task Interface Agreement 2006-002 Replacement of Reactor Relief Valves with Valves Not Qualified in Accordance with Section 50.49 of Title 10 of Code of Federal Regulations (10 CFR) | |
ML070180219 | 17 January 2007 | GFE Annual Registration Letter - 2007 Examinations | Generic Fundamentals Examination |
ML070120260 | 17 January 2007 | Quad Cites & Three Mile Island Nuclear Station, Revision of Emergency Action Levels in Radiological Emergency Response Plan | |
TAC:MD4008 | 16 January 2007 | ||
ML070230540 | 16 January 2007 | NF-BEX-06-281, Rev 0, Quad Cities, Unit 1 Cycle 20 SLMCPR, NP-Attachement | Minimum Critical Power Ratio |
RS-07-012, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit | 16 January 2007 | Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit | Shutdown Margin Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Fuel cladding |
SVP-07-001, CFR 50.59/10 CFR 72.48 Summary Report for January 2004 to December 31, 2006 | 3 January 2007 | CFR 50.59/10 CFR 72.48 Summary Report for January 2004 to December 31, 2006 | Anticipated operational occurrence Turbine Missile Fuel cladding Flow Induced Vibration |