Category:Letter type:RS

R

• RS-01-112, Registration of Use of Cask to Store Spent Fuel at Dresden, Units 1, 2 & 3
• RS-02-000, Virgil C Summer Nuclear Station, Technical Specification Amendment Request - TSP 00-0032 Revision to Engineered Safety Feature Actuation System Instrumentation Tables - Supplemental Letter
• RS-02-002, Registration of Use of Cask to Store Spent Fuel
• RS-02-004, Response to Request for Additional Information Regarding a Second Interval Inservice Testing Program Relief Request, PR-2
• RS-02-005, Additional Mechanical Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation
• RS-02-009, Completion of Power Uprate Modifications
• RS-02-010, Additional Information Supporting Technical Specification Changes to Reactor Pressure Vessel Level Instrumentation Surveillance Frequencies and Allowable Values Requirements
• RS-02-011, Additional Testing Information Supporting the License Amendment Request to Permit Uprated Power Operation
• RS-02-012, Revised Technical Specification Pages for the License Amendment Request Associated with DC Electrical Power
• RS-02-013, Response to Request for Additional Information Regarding Risk Aspects of Inclined Fuel Transfer System License Amendment Request for Clinton Power Station
• RS-02-014, Additional Mechanical Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation
• RS-02-015, Communications with NRC Re Quad Cities, Unit 1 Jet Pump Hold Down Beam Replacement Activities & Continued Operation of Quad Cities, Unit 2 & Dresden, Units 2 & 3
• RS-02-018, Supplement to 06/21/2001 License Amendment Request, Surveillance Requirements for Main Steam Line Safety Relief Valves
• RS-02-019, Supplemental Reactor Systems Information Supporting License Amendment Request to Permit Uprated Power Operation at Clinton Power Station
• RS-02-021, Response to Request for Additional Information Re Previous License Amendment Request to Revise Fuel Centerline Temperature Safety Limit for Byron & Braidwood Stations
• RS-02-024, Amergen Response to Request for Additional Information Re risk-informed Inservice Inspection Program
• RS-02-026, Update Concerning Jet Pump Hold Down Beam Activities
• RS-02-027, Request for Technical Specifications Change, Revision to Technical Specification 3.7.1, Main Steam Safety Valve (Mssvs).
• RS-02-033, Relief Request for Alternative Rules for Corrective Measures If Leakage Occurs at Bolted Connections During System Pressure Tests
• RS-02-034, Withdrawal of Request for NRC Approval of Physical Security & Guard Force Training & Qualification Plan Changes
• RS-02-035, Supplemental Information Supporting the Request for Exemption from the Secondary Offsite Accident Liability Insurance Requirement of 10 CFR 140.11(a)(4)
• RS-02-039, Request for Approval of Pipe Flaw Evaluation
• RS-02-044, Request for Technical Specification Change, Revises Emergency Diesel Generator Required Start Time
• RS-02-046, Additional Information Supporting Request for Approval of Pipe Flaw Evaluation
• RS-02-047, Supplemental Information Supporting a License Amendment Request to Revise Plant System Requirements During Fuel Handling Based on Alternative Source Term
• RS-02-051, Response to Request for Additional Information Re Review and Approval of Changes to Emergency Action Level Classification Schemes
• RS-02-053, Supplemental Information Supporting Request for Approval of Pipe Flaw Evaluation
• RS-02-055, Response to Commission Order to Modify License for Interim Safeguards & Security Measures
• RS-02-057, Feedwater Nozzle Safe End Fatigue Evaluation Supporting the License Amendment Request to Permit Uprated Power Operations
• RS-02-058, Review of Draft Power Uprate Safety Evaluation
• RS-02-059, Submittal of Security Plan, Revision 67 for LaSalle County Station, Units 1 & 2. No Enclosures
• RS-02-061, Three Mile, Unit 1, Braidwood, Units 1 & 2, Byron, Units 1 & 2 - Exelon/Amergen Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
• RS-02-062, Revised Risk Analysis Sensitivity Case Support the License Amendment Request to Permit Extended Power Uprate Operation for Clinton Power Station
• RS-02-065, Hot Leg Switchover Confirmatory Analysis Supporting Uprated Power Operations
• RS-02-067, Power Uprate Ascension Test Report
• RS-02-068, Response to Request for Additional Information Re Proposed Power Uprate
• RS-02-071, Request for Approval of Quality Assurance Program Changes for Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Nuclear Power Plants
• RS-02-072, Response to Request for Additional Information Regarding Risk Informed Inservice Inspection Relief Request
• RS-02-074, Second 10-Year Inservice Inspection Interval End Dates
• RS-02-075, Withdrawal of Request for NRC Approval of Changes to Emergency Plan
• RS-02-078, Response to Request for Additional Information on Review of Proposed Emergency Action Level Classification Schemes, Clinton Power Station Unit 1
• RS-02-081, Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for light-water Nuclear Power Reactors
• RS-02-082, Station'S Response to Request for Additional Information Re Heavy Loads Handling
• RS-02-085, Security Plan, Revision 55
• RS-02-091, Exelon/Amergen Sixty-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
• RS-02-093, Registration of Use of Cask to Store Spent Fuel
• RS-02-096, Completion of Power Uprate Modifications for Clinton Power Station Unit 1
• RS-02-098, Long Term Storage of High Pressure and Low Pressure Turbine Components at Clinton Power Station, Unit 1
• RS-02-102, Additional Information Regarding License Amendment Request to Eliminate Requirement for Continuous Control Room Watch When Nuclear Fuel Stored in Spent Fuel Pool
• RS-02-103, Supplemental Information Supporting Changes to Technical Specifications for Anticipated Transient Without Scram Recirculation Pump Trip System
• RS-02-104, Registration of Use of Cask to Store Spent Fuel
• RS-02-106, Security Plan, Revision 34
• RS-02-110, Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation.
• RS-02-111, Registration of Use of Cask to Store Spent Fuel
• RS-02-119, Request for Amendment to Technical Specification 3.2.2, Minimum Critical Power Ratio (Mcpr), Addition of a New Surveillance Requirement
• RS-02-122, Justification for Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure & Temperature (P/T) Limits.
• RS-02-123, Response to Regulatory Issue Summary 2002-09, Preparation and Scheduling of Operator Licensing Examinations.
• RS-02-124, Additional Information Regarding Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Reactor Vessel Steam Dome Pressure - High)
• RS-02-125, Letter from Patrick R. Simpson Subject: Supplement to Response to Request for Additional Information Regarding Heavy Loads Handling
• RS-02-126, Supplemental Information Supporting Request for Technical Specification Changes for Minimum Critical Power Ratio Safety Limit
• RS-02-128, Request for Exemption from Certain Requirements of 10 CFR 55.59
• RS-02-129, Revision to Request for Exemption from 10CFR 55.59
• RS-02-132, Submittal of Power Uprate Ascension Test Report for Quad Cities Nuclear Power Station, Unit 2
• RS-02-133, Partial Withdrawal of Request for NRC Approval of Amendment to Permit Continued Fuel Movement with Inoperable Refueling Equipment Interlocks
• RS-02-137, Power Uprate Ascension Test Report
• RS-02-140, Supplemental Response to Commission Order to Modify License for Interim Safeguards and Security Measures for Interim Compensatory Measure B.4.e
• RS-02-141, Revised Response to Regulatory Issue Summary 2002-09, Preparation and Scheduling of Operator Licensing Examinations.
• RS-02-143, Units 1 & 2 Additional Information Supporting License Amendment Request on Technical Specifications Surveillance Requirement for Containment Spray Nozzles
• RS-02-145, Supplemental Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit
• RS-02-146, Revised Supplemental Response to Commission Order to Modify License for Interim Safeguards & Security Measures for Interim Compensatory Measure B.4.e
• RS-02-148, Long Term Solution Stability System Oscillation Power Range Monitor Revised Implementation Plan
• RS-02-150, Additional Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power Operations
• RS-02-151, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)
• RS-02-154, Exelon/Amergen Thirty-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
• RS-02-155, Response to NRC Inspection Items Regarding Concrete Expansion Anchors
• RS-02-156, Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2SI8811A/B
• RS-02-158, Confirmation of Completion of Actions Implementing the Interim Compensatory Measures of the February 25, 2002, Commission Order to Modify License for Interim Safeguards and Security Measures
• RS-02-160, Request for Amendment to TS 5.6.5, Core Operating Limits Report for Addition of New Analytical Methodology
• RS-02-163, Additional Information Supporting License Amendment Request to Revise Suppression Pool Water Level & Upper Containment Pool Water Level Requirements in Mode 3
• RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.
• RS-02-165, Response to Request for Additional Information Re Excess Flow Check Valve Testing Surveillance and Relief Request RV-12
• RS-02-167, Request for Amendment to Technical Specifications Justification for the Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure and Temperature (P/T) Limits.
• RS-02-168, Request for License Amendment Related to Heavy Loads Handling
• RS-02-169, Request for License Amendment Related to Appendix B, Environmental Protection Plan (Non-Radiological)
• RS-02-171, Request for License Amendment Related to Heavy Loads Handling
• RS-02-173, Request for License Amendment to Add Technical Specification Surveillance Requirement for Diesel Driven Auxiliary Feedwater Pump
• RS-02-175, Request for Technical Specification Changes Related to Main Steam Safety Valve Operability Requirements
• RS-02-179, Request for Technical Specification Change Extension of Completion Time for Instrument Bus Inverters
• RS-02-181, Submittal of Revision 2 to Defueled Safety Analysis Report Update
• RS-02-182, Letter Regards Additional Information Supporting Request for TS Change for Minimum Critical Power Ratio Safety Limit
• RS-02-185, Additional Information Regarding Request for License Amendment Related to Heavy Loads Handling
• RS-02-187, Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii) Regarding Control Rod Drive Housing Welds (Relief Request Number CR-25)
• RS-02-189, Withdrawal of Requested Amendment to Technical Specifications Excess Flow Check Valve Testing Surveillance and Relief Request RV-12
• RS-02-191, Revision 13 to Standardized Radiological Emergency Plan Annex
• RS-02-194, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
• RS-02-196, Revised Request for Amendment to Technical Specifications Justification for the Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure and Temperature (P/T) Limits.
• RS-02-197, Reply to Request for Comments on Draft Response to Task Interface Agreement Concerning the Reactor Building Crane and Heavy Loads Handling
• RS-02-203, Response to Request for Additional Information Regarding a License Amendment Request to Modify the Method of Controlling Unfavorable Exposure Time Related to an Anticipated Transient Without Scram Event
• RS-02-205, Response to Request for Additional Information Supporting a License Amendment Request Revising TS Surveillance Requirements for Containment Spray Nozzles
• RS-02-208, Completion of Power Uprate Modifications for Dresden, Unit 3 and Quad Cities, Unit 1
• RS-02-210, Revisions to Exelon Nuclear Standardized Radiological Emergency Plan Annexes & Implementing Procedure
• RS-02-214, Response to Request for Additional Information Addressing Request for Amendment to Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Addition of New Analytical Methodology
• RS-02-215, Request for License Amendment to Eliminate Main Steam Isolation Valve Closure & Low Condenser Vacuum Scram Functions During Startup Mode
• RS-03-004, Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/B
• RS-03-006, Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis.
• 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.
• 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
• RS-03-013, Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program
• RS-03-014, Power Uprate Ascension Test Report
• RS-03-016, 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
• RS-03-018, 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
• RS-03-023, Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit
• RS-03-025, Licensed Thermal Power Limit Verification
• RS-03-026, 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.
• RS-03-034, 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
• RS-03-037, Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for Second 10-Year Inservice Testing Program
• RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function
• RS-03-040, Request for Amendment to Technical Specifications Section 5.7, High Radiation Area.
• RS-03-041, 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.
• 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).
• 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
• 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
• RS-03-051, Additional Information Supporting Request for License Amendment Regarding Minimum Critical Power Ratio Safety Limit
• RS-03-052, 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
• 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.
• RS-03-060, Request for License Amendment Related to Application of Alternative Source Term
• RS-03-061, Revision to Exelon Nuclear Standardized Radiological Emergency Plan & Emergency Plan Procedure
• 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
• RS-03-063, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term
• RS-03-064, Request for a License Amendment to Revise the Pressurizer Safety Valves Lift Settings
• RS-03-066, 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
• RS-03-068, 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
• 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
• RS-03-072, 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
• 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.
• RS-03-075, 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
• RS-03-077, Proposed Alternative Method of Repair for Control Rod Drive Mechanism Canopy Seal Weld
• RS-03-079, Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing
• RS-03-081, Request for License Amendment for Core Flow Operating Range Expansion & Oscillation Power Range Monitor (OPRM) Instrumentation
• 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
• RS-03-088, 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
• RS-03-091, Additional Information Regarding Relief Request RV-30E
• RS-03-094, Clinton Power Station, Unit 1, Oyster Creek Generating Station, Three Mile Island Nuclear Station, Unit 1, Revised Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization
• RS-03-095, Revised Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization
• RS-03-097, Units 1 & 2 - Response to RAI Technical Specifications Change Request - Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)
• RS-03-099, Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program
• RS-03-100, Additional Information Supporting the Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Relief Request RV-30E
• RS-03-101, Additional Information Regarding Inservice Inspection Program Relief Request I4R-02
• RS-03-105, Additional Information Supporting Request or License Amendment to Eliminate Main Steam Isolation Valve Closure and Low Condenser Vacuum Scram Functions During Startup Mode
• RS-03-106, Supplement to Request for Amendment to TS Surveillance Requirement 3.6.1.3.8
• RS-03-107, Response to Task Interface Agreement 2001-14, Evaluation of LaSalle Water Hammer Analysis, Revision 1.
• RS-03-110, Response to Issuance of Orders to Modify License for Revised Design Basis Threat and Compensatory Measures Related to Security Force Training and Fitness-for-Duty
• RS-03-112, Request for Amendment to Technical Specifications Section 5.6.5 Core Operating Limits Report (Colr).
• RS-03-113, Reactor Coolant System Pressure & Temperature Limits
• RS-03-114, Registration of Use of Cask to Store Spent Fuel
• RS-03-115, Additional Information Regarding Request for License Amendment Related to Heavy Loads Handling
• RS-03-116, Request for Technical Specifications Change Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.
• RS-03-121, Registration of Use of Cask to Store Spent Fuel
• RS-03-122, Response to Request for Additional Information to Support Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.
• RS-03-123, Response to Request for Additional Information to Support Request for Amendment to TS Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation
• RS-03-124, Revisions to Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedure
• RS-03-127, Commitments for Resolution of Steam Dryer Degradation Issue
• RS-03-128, Registration of Use of Cask to Store Spent Fuel
• RS-03-131, Additional Information Supporting Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program
• RS-03-135, Additional Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program, Clinton Power Station, Unit 1
• RS-03-136, Request to Withhold Information from Public Disclosure
• RS-03-137, Schedule for Completing Committed Actions Regarding Resolution of Steam Dryer Degradation Issue
• RS-03-140, Request for Amendment to Technical Specifications Associated with Direct Current Electrical Power
• RS-03-142, Additional Information Regarding Request for License Amendment for Pressure-Temperature Limits for Dresden Nuclear Power Station, Units 2 and 3
• RS-03-144, Registration of Use of Cask to Store Spent Fuel
• RS-03-145, Request for Amendments to TS Section 5.5.13, Primary Containment Leakage Rate Testing Program
• RS-03-146, Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors, Dated 06/09/03
• RS-03-147, Additional Information Regarding the Request for License Amendment Related to Heavy Loads Handling
• RS-03-149, Licensed Thermal Power Limit Verification
• RS-03-152, Supplemental Response to Issuance of Order to Modify License and Compensatory Measures Related to Security Force Fitness-for-Duty
• RS-03-153, Transmittal of Dresden Nuclear Power Station, Units 2 and 3, Additional Information Regarding Request for License Amendment for Pressure Temperature Limits
• RS-03-154, Exelon/Amergen 60-Day Response to NRC Generic Letter 2003-01, Control Room Habitability.
• RS-03-155, Additional Information Supporting Request for License Amendment Related to Application of Alternative Source Term
• RS-03-157, Additional Information Regarding Inservice Testing Program Relief Requests
• RS-03-159, Revisions to the Exelon Nuclear Standardized Radiological Emergency Plan Implementing Procedure
• RS-03-160, Additional Information Supporting the Request for Amendment to Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program.
• RS-03-161, Transmittal of General Electric Technical Assessment Regarding Quad Cities Nuclear Power Station Unit 2 Steam Dryer Failure
• RS-03-163, Response to Request for Additional Information Regarding Fourth Interval Inservice Inspection Program Plan
• RS-03-164, Supplemental Information Supporting License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power Operations
• RS-03-165, Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing
• RS-03-166, Update to Information Supporting License Amendment Request to Permit Uprated Power Operation at Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2
• RS-03-169, Additional Information Supporting the Request for Amendment to Technical Specifications 3.2.2, Minimum Critical Power Ratio (Mcpr), Addition of a New Surveillance Requirement
• RS-03-170, Registration of First Use of Cask to Transport Spent Fuel
• RS-03-171, Request for License Amendment Related to Heavy Loads Handling