RS-03-004, Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/B | 23 January 2003 | Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/B | Stroke time Probabilistic Risk Assessment |
RS-03-006, Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis. | 13 January 2003 | Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis. | Safe Shutdown Significance Determination Process Pressure Boundary Leakage Backfit |
RS-03-007, Exelon/Amergen Response to Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | 21 January 2003 | Exelon/Amergen Response to Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | Boric Acid Non-Destructive Examination Hydrostatic VT-2 Pressure Boundary Leakage Dissimilar Metal Weld Scaffolding |
RS-03-009, Request for Exemption from Provisions of 10 CFR 50.44, 10 CFR 50.46 & 10 CFR 50 Appendix K for One Lead Test Assembly, & Request for an Increase in Rod-Average Burnup Limit for Four Fuel Assemblies | 17 January 2003 | Request for Exemption from Provisions of 10 CFR 50.44, 10 CFR 50.46 & 10 CFR 50 Appendix K for One Lead Test Assembly, & Request for an Increase in Rod-Average Burnup Limit for Four Fuel Assemblies | Exemption Request Fuel cladding Coast down |
RS-03-013, Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program | 29 January 2003 | Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program | Safe Shutdown High winds Internal Flooding Probabilistic Risk Assessment Coatings Large early release frequency Exemption Request Earthquake |
RS-03-014, Power Uprate Ascension Test Report | 23 January 2003 | Power Uprate Ascension Test Report | Shutdown Margin Flow Induced Vibration |
RS-03-016, Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | 27 January 2003 | Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | |
RS-03-017, Unit 1, Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | 27 January 2003 | Unit 1, Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | |
RS-03-018, Proposed Alternative Testing Requirements for Containment Isolation Check Valves 1C11-F122 & 1/a175 for Second 10-Year Inservice Testing Program | 3 February 2003 | Proposed Alternative Testing Requirements for Containment Isolation Check Valves 1C11-F122 & 1/a175 for Second 10-Year Inservice Testing Program | |
RS-03-019, Power Uprate Ascension Test Report for Quad Cities Nuclear Power Station, Unit 1 | 4 February 2003 | Power Uprate Ascension Test Report for Quad Cities Nuclear Power Station, Unit 1 | Flow Induced Vibration |
RS-03-023, Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit | 31 January 2003 | Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Fuel cladding |
RS-03-025, Licensed Thermal Power Limit Verification | 5 February 2003 | Licensed Thermal Power Limit Verification | |
RS-03-026, Request for TS Changes Related to Primary Containment Isolation Instrumentation for the Isolation Condenser System | 31 January 2003 | Request for TS Changes Related to Primary Containment Isolation Instrumentation for the Isolation Condenser System | |
RS-03-029, Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation. | 31 March 2003 | Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation. | |
RS-03-034, Delegation of Authority of Amergen Energy Company, LLC (Amergen) Nuclear Power Plants | 6 February 2003 | Delegation of Authority of Amergen Energy Company, LLC (Amergen) Nuclear Power Plants | |
RS-03-036, Request for TS Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing | 14 February 2003 | Request for TS Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing | Hydrostatic Squib |
RS-03-037, Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for Second 10-Year Inservice Testing Program | 14 February 2003 | Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for Second 10-Year Inservice Testing Program | Stroke time Temporary Modification |
RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function | 28 March 2003 | Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio |
RS-03-040, Request for Amendment to Technical Specifications Section 5.7, High Radiation Area. | 31 March 2003 | Request for Amendment to Technical Specifications Section 5.7, High Radiation Area. | High Radiation Area |
RS-03-041, Answer to NRC Order to Modify Licensees Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads | 28 February 2003 | Answer to NRC Order to Modify Licensees Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads | |
RS-03-044, Request for Amendment to Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program. | 27 February 2003 | Request for Amendment to Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program. | Safe Shutdown High winds Internal Flooding Probabilistic Risk Assessment Coatings Large early release frequency Earthquake |
RS-03-047, Response to a Request for Additional Information Regarding a Technical Specifications Change Request - Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs). | 28 February 2003 | Response to a Request for Additional Information Regarding a Technical Specifications Change Request - Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs). | Anticipated operational occurrence |
RS-03-048, Additional Information in Support of Request for Amendment to Technical Specification 3.2.2 Minimum Critical Power Ratio (MCPR) Addition of New Surveillance Requirement | 7 March 2003 | Additional Information in Support of Request for Amendment to Technical Specification 3.2.2 Minimum Critical Power Ratio (MCPR) Addition of New Surveillance Requirement | |
RS-03-049, Withdrawal of Request for a License Amendment to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event | 13 March 2003 | Withdrawal of Request for a License Amendment to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event | |
RS-03-051, Additional Information Supporting Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit | 7 March 2003 | Additional Information Supporting Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit | Anticipated operational occurrence Minimum Critical Power Ratio |
RS-03-052, EA-02-124, 4/11/2003, Exelon Description of Results of Work Environment Review | 11 April 2003 | EA-02-124, 4/11/2003, Exelon Description of Results of Work Environment Review | |
RS-03-053, Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term | 28 March 2003 | Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term | Boric Acid |
RS-03-054, Response to Request for Additional Information Related to NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions. | 20 March 2003 | Response to Request for Additional Information Related to NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions. | |
RS-03-060, Request for License Amendment Related to Application of Alternative Source Term | 3 April 2003 | Request for License Amendment Related to Application of Alternative Source Term | Shutdown Margin Safe Shutdown Earthquake Probabilistic Risk Assessment Excess Flow Check Valve Deep Dose Equivalent Recently irradiated fuel Power Uprate Affidavit |
RS-03-061, Revision to Exelon Nuclear Standardized Radiological Emergency Plan & Emergency Plan Procedure | 24 March 2003 | Revision to Exelon Nuclear Standardized Radiological Emergency Plan & Emergency Plan Procedure | Fitness for Duty Nuclear Accident Reporting System Severe Accident Management Guideline |
RS-03-062, Response to Request for Additional Information Related to a Request for Exemption from the Provisions of 10 CFR 50.44, 10 CFR 50.46 and 10 CFR 50 Appendix K | 24 March 2003 | Response to Request for Additional Information Related to a Request for Exemption from the Provisions of 10 CFR 50.44, 10 CFR 50.46 and 10 CFR 50 Appendix K | Exemption Request |
RS-03-063, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term | 21 March 2003 | Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term | Severe Accident Management Guideline |
RS-03-064, Request for a License Amendment to Revise the Pressurizer Safety Valves Lift Settings | 27 June 2003 | Request for a License Amendment to Revise the Pressurizer Safety Valves Lift Settings | Loop seal |
RS-03-066, Additional Information Supporting License Amendment Request to Revise Suppression Pool Water Level Upper Containment Pool Water Level Requirements in Mode 3 | 28 March 2003 | Additional Information Supporting License Amendment Request to Revise Suppression Pool Water Level Upper Containment Pool Water Level Requirements in Mode 3 | |
RS-03-067, Revised Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | 26 March 2003 | Revised Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | |
RS-03-068, Revised Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | 26 March 2003 | Revised Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization | |
RS-03-069, Supplemental Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power Operations | 28 March 2003 | Supplemental Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power Operations | Safe Shutdown Safe Shutdown Earthquake Hydrostatic Anchor Darling Seismically rugged Earthquake |
RS-03-070, Additional Information Supporting the Request for License Amendment to Eliminate Main Steam Isolation Valve Closure and Low Condenser Vacuum Scram Functions During Startup Mode | 28 March 2003 | Additional Information Supporting the Request for License Amendment to Eliminate Main Steam Isolation Valve Closure and Low Condenser Vacuum Scram Functions During Startup Mode | |
RS-03-072, Unit 1, Report on Status of Decommissioning Funding for Reactors | 31 March 2003 | Unit 1, Report on Status of Decommissioning Funding for Reactors | |
RS-03-073, Report on Status of Decommissioning Funding for Reactors, Braidwood, Units 1 & 2, Byron, Units 1 & 2, Dresden, Units 1, 2 & 3, LaSalle, Units 1 & 2, Limerick, Units 1 & 2, Peach Bottom, Units 1, 2 & 3 Salem, Units 1 & 2, Quad Cities, Units | 31 March 2003 | Report on Status of Decommissioning Funding for Reactors, Braidwood, Units 1 & 2, Byron, Units 1 & 2, Dresden, Units 1, 2 & 3, LaSalle, Units 1 & 2, Limerick, Units 1 & 2, Peach Bottom, Units 1, 2 & 3 Salem, Units 1 & 2, Quad Cities, Units | |
RS-03-074, Units 1 & 2 - Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. | 14 April 2003 | Units 1 & 2 - Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. | |
RS-03-075, Request for Amendment to TS Table 3.3.6.1-1, Primary Containment Isolation Instrumentation | 18 April 2003 | Request for Amendment to TS Table 3.3.6.1-1, Primary Containment Isolation Instrumentation | |
RS-03-076, Additional Information Supporting TS Changes to Reactor Protection System Instrumentation Scram Discharge Volume Water Level - High | 7 April 2003 | Additional Information Supporting TS Changes to Reactor Protection System Instrumentation Scram Discharge Volume Water Level - High | Scram Discharge Volume |
RS-03-077, Proposed Alternative Method of Repair for Control Rod Drive Mechanism Canopy Seal Weld | 23 April 2003 | Proposed Alternative Method of Repair for Control Rod Drive Mechanism Canopy Seal Weld | Weld Overlay Nondestructive Examination VT-2 Liquid penetrant |
RS-03-079, Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing | 19 May 2003 | Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing | Safety Limit Minimum Critical Power Ratio Feedwater Controller Failure |
RS-03-081, Request for License Amendment for Core Flow Operating Range Expansion & Oscillation Power Range Monitor (OPRM) Instrumentation | 1 May 2003 | Request for License Amendment for Core Flow Operating Range Expansion & Oscillation Power Range Monitor (OPRM) Instrumentation | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Safe Shutdown Earthquake Post Accident Monitoring Abnormal operational transient Scram Discharge Volume Annual Radiological Environmental Operating Report Process Control Program Earthquake Fuel cladding |
RS-03-083, Additional Information Supporting Request for Amendment to Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program. Reflects One-time Deferral of Primary Containment Type a Test | 11 April 2003 | Additional Information Supporting Request for Amendment to Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program. Reflects One-time Deferral of Primary Containment Type a Test | Moisture barrier |
RS-03-088, Clarification of Commitment Regarding Request for Relief | 30 April 2003 | Clarification of Commitment Regarding Request for Relief | |
RS-03-090, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Relief Valves and Relief Request RV-30E | 1 May 2003 | Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Relief Valves and Relief Request RV-30E | Stroke time Foreign Material Exclusion |
RS-03-091, Additional Information Regarding Relief Request RV-30E | 2 May 2003 | Additional Information Regarding Relief Request RV-30E | |