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 Issue dateTitleTopic
RS-03-004, Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/B23 January 2003Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/BStroke time
Probabilistic Risk Assessment
RS-03-006, Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis.13 January 2003Response 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 2003Exelon/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 Assemblies17 January 2003Request 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 AssembliesExemption 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 Program29 January 2003Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing ProgramSafe Shutdown
High winds
Internal Flooding
Probabilistic Risk Assessment
Coatings
Large early release frequency
Exemption Request
Earthquake
RS-03-014, Power Uprate Ascension Test Report23 January 2003Power Uprate Ascension Test ReportShutdown Margin
Flow Induced Vibration
RS-03-016, Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization27 January 2003Response 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 Authorization27 January 2003Unit 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 Program3 February 2003Proposed 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 14 February 2003Power Uprate Ascension Test Report for Quad Cities Nuclear Power Station, Unit 1Flow Induced Vibration
RS-03-023, Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit31 January 2003Request for License Amendment Regarding Minimum Critical Power Ratio Safety LimitReactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Fuel cladding
RS-03-025, Licensed Thermal Power Limit Verification5 February 2003Licensed Thermal Power Limit Verification
RS-03-026, Request for TS Changes Related to Primary Containment Isolation Instrumentation for the Isolation Condenser System31 January 2003Request 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 2003Request 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 Plants6 February 2003Delegation 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 Testing14 February 2003Request for TS Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve TestingHydrostatic
Squib
RS-03-037, Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for Second 10-Year Inservice Testing Program14 February 2003Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for Second 10-Year Inservice Testing ProgramStroke time
Temporary Modification
RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function28 March 2003Request for Amendment to TS for Main Steam Line Low Pressure Isolation FunctionReactor 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 2003Request 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 Heads28 February 2003Answer 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 2003Request 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 2003Response 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 Requirement7 March 2003Additional 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 Event13 March 2003Withdrawal 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 Limit7 March 2003Additional Information Supporting Request for License Amendment Regarding Minimum Critical Power Ratio Safety LimitAnticipated operational occurrence
Minimum Critical Power Ratio
RS-03-052, EA-02-124, 4/11/2003, Exelon Description of Results of Work Environment Review11 April 2003EA-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 Term28 March 2003Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source TermBoric 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 2003Response 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 Term3 April 2003Request for License Amendment Related to Application of Alternative Source TermShutdown 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 Procedure24 March 2003Revision to Exelon Nuclear Standardized Radiological Emergency Plan & Emergency Plan ProcedureFitness 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 K24 March 2003Response 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 KExemption Request
RS-03-063, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term21 March 2003Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source TermSevere Accident Management Guideline
RS-03-064, Request for a License Amendment to Revise the Pressurizer Safety Valves Lift Settings27 June 2003Request for a License Amendment to Revise the Pressurizer Safety Valves Lift SettingsLoop seal
RS-03-066, Additional Information Supporting License Amendment Request to Revise Suppression Pool Water Level Upper Containment Pool Water Level Requirements in Mode 328 March 2003Additional 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 Authorization26 March 2003Revised 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 Authorization26 March 2003Revised 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 Operations28 March 2003Supplemental Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power OperationsSafe 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 Mode28 March 2003Additional 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 Reactors31 March 2003Unit 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, Units31 March 2003Report 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 2003Units 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 Instrumentation18 April 2003Request 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 - High7 April 2003Additional Information Supporting TS Changes to Reactor Protection System Instrumentation Scram Discharge Volume Water Level - HighScram Discharge Volume
RS-03-077, Proposed Alternative Method of Repair for Control Rod Drive Mechanism Canopy Seal Weld23 April 2003Proposed Alternative Method of Repair for Control Rod Drive Mechanism Canopy Seal WeldWeld 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 Testing19 May 2003Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve TestingSafety 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) Instrumentation1 May 2003Request for License Amendment for Core Flow Operating Range Expansion & Oscillation Power Range Monitor (OPRM) InstrumentationSafety 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 Test11 April 2003Additional 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 TestMoisture barrier
RS-03-088, Clarification of Commitment Regarding Request for Relief30 April 2003Clarification 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-30E1 May 2003Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Relief Valves and Relief Request RV-30EStroke time
Foreign Material Exclusion
RS-03-091, Additional Information Regarding Relief Request RV-30E2 May 2003Additional Information Regarding Relief Request RV-30E