Category:Letter type:RS

R

• RS-01-112, Registration of Use of Cask to Store Spent Fuel at Dresden, Units 1, 2 & 3
• RS-01-235, License Renewal: Request for Information on Threatened or Endangered Species
• RS-01-285, License Renewal: Request for Information on Thermophilic Microorganisms
• RS-01-286, License Renewal: Request for Information on Thermophilic Microorganisms
• RS-01-293, License Renewal: Request for Information in Historic/Archeological Resources
• 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, 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-02-079, NRC - Scott County - RS-02-079 - Quad Cities Nuclear Power Station Units 1 & 2 License Renewal - Power Station License Renewal Review - Additional Correspondence from NRC
• 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, Stations 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, 3 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-03-039, Request for Changes Related to TS Section 3.4.9, Reactor Coolant System Pressure & Temperature (P/T) Limits
• 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-03-082, Corrected Fluence Tables for Dresden Units 2 & 3 License Renewal Application
• 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, 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-03-098, Supplemental Information for Analysis of Transmission Lines in Quad Cities Nuclear Power Station License Renewal Application
• 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-03-108, Additional Information Regarding Environmental Review of License Renewal Applications
• 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-03-132, Response to Request for Additional Information - License Renewal Environmental Report
• RS-03-133, Response to Request for Additional Information - License Renewal Environmental Report for Dresden Nuclear Power Station, Units 2 and 3
• 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