Primary containment

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Primary Containment is the 3rd barrier to stop the release of radiological material. It is typically called the Drywell and Suppression Chamber

 SiteStart dateReporting criterionTitle
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC QuestionsWolf Creek31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and ControlsWolf Creek31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety FeaturesWolf Creek31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan RequirementsWolf Creek31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the PlantWolf Creek31 May 2016Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant
WM 16-0008, Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, Calculation No. XX-E-013, Rev 4, Post-Fire Safe Shutdown AnalysisWolf Creek31 May 2016Wolf Creek Generating Station Updated Safety Analysis Report (Usar), Redacted Version of Revision 29, Calculation No. XX-E-013, Rev 4, Post-Fire Safe Shutdown Analysis
WM 10-0017, Wolf Creek, Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical CableWolf Creek2 June 2010Wolf Creek, Response to Request for Additional Information Related to License Amendment Request for Use of Fire-Resistive Electrical Cable
ULNRC-06238, Callaway, Unit 1 - Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6Callaway31 August 2015Callaway, Unit 1 - Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6
ULNRC-06230, Callaway, Unit 1 - Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6Callaway16 July 2015Callaway, Unit 1 - Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6
ULNRC-06166, Callaway, Unit 1, Technical Position TP-06 Position Indication Testing of EMHV8924Callaway19 December 2014Callaway, Unit 1, Technical Position TP-06 Position Indication Testing of EMHV8924
ULNRC-06166, Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing ProgramCallaway19 December 2014Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program
ULNRC-06035, Callaway, Unit 1, 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests (TAC No. MF2642)Callaway29 August 2013Callaway, Unit 1, 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements Regarding the Frequency of Inservice Tests (TAC No. MF2642)
ULNRC-06034, Callaway, Unit 1 - 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fourth 120-Month Inservice Testing IntervalCallaway23 September 2013Callaway, Unit 1 - 10 CFR 50.55a(a)(3) Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fourth 120-Month Inservice Testing Interval
ULNRC-05947, Callaway Plant, Unit 1, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal ApplicationCallaway15 January 2013Callaway Plant, Unit 1, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal Application
ULNRC-05908, Callaway, Unit 1, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation AlternativesCallaway24 September 2012Callaway, Unit 1, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives
ULNRC-05830, Callaway, Unit 1, Environmental Report; Operating License Renewal Stage Final, Attachment E Through EndCallaway15 December 2011Callaway, Unit 1, Environmental Report; Operating License Renewal Stage Final, Attachment E Through End
ULNRC-05821, Callaway Plant, Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173)Callaway27 October 2011Callaway Plant, Union Electric Co. Application for Amendment to Facility Operating License NPF-30 (Ldcn 10-0036) Revision of Technical Specification 3.3.8 TAC ME5173)
ULNRC-05781, Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2Callaway29 August 2011Callaway Plant NFPA 805 Transition Report, Attachment a - NEI 04-02 Table B-1 and Attachment B - NEI 04-02 Table B-2
ULNRC-05598, Callaway, Unit 1, Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request Ldcn 09-0008)Callaway20 March 2009Callaway, Unit 1, Proposed Revision to Technical Specification 5.5.16 Containment Leakage Rate Testing Program, (License Amendment Request Ldcn 09-0008)
ULNRC-05309, Callaway, Unit 1 - Inoperable Channel 11 of the Loose Parts Detection System (Lpds)Callaway10 July 2006Callaway, Unit 1 - Inoperable Channel 11 of the Loose Parts Detection System (Lpds)
ULNRC-05248, Callaway Plant Submittal of Revision 23 to Pump and Valve Inservice Testing ProgramCallaway19 January 2006Callaway Plant Submittal of Revision 23 to Pump and Valve Inservice Testing Program
ULNRC-05237, Callaway, Unit 1 - Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)Callaway9 December 2005Callaway, Unit 1 - Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)
TSTF-17-16, Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2Technical Specifications Task Force19 December 2017Technical Specifications Task Force - Transmittal of TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
TSTF-17-10, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements.Technical Specifications Task Force2 August 2017TSTF Comments on Draft Safety Evaluation for Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements.
TSTF-16-10, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control, and Transmittal of Editorial Corrections to TSTF-542, Revision 2Technical Specifications Task Force2 November 2016TSTF Comments on Draft Safety Evaluation for Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control, and Transmittal of Editorial Corrections to TSTF-542, Revision 2
TSTF-14-17, Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3Technical Specifications Task Force31 March 2015Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3
TSTF-13-03, Transmittal of TSTF-529, Revision 1, Clarify Use and Application RulesTechnical Specifications Task Force28 February 2013Transmittal of TSTF-529, Revision 1, Clarify Use and Application Rules
TSTF-13-02, Submittal of TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.Technical Specifications Task Force21 February 2013Submittal of TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.
TSTF-12-15, Response to NRC Request for Additional Information Regarding TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation.Technical Specifications Task Force30 August 2012Response to NRC Request for Additional Information Regarding TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation.
TSTF-12-11, Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6)Technical Specifications Task Force16 May 2012Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6)
TSTF-12-08, Transmittal of TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas AccumulationTechnical Specifications Task Force29 March 2012Transmittal of TSTF-523, Revision 1, Generic Letter 2008-01, Managing Gas Accumulation
TSTF-12-05, Transmittal of Report TSTF-GG-05-01, Revision 1, Writer'S Guide for Plant-Specific Improved Technical Specifications.Technical Specifications Task Force14 February 2012Transmittal of Report TSTF-GG-05-01, Revision 1, Writer'S Guide for Plant-Specific Improved Technical Specifications.
TSTF-12-04, Transmittal of TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373Technical Specifications Task Force27 March 2012Transmittal of TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373
TSTF-12-01, Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046).Technical Specifications Task Force22 February 2012Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046).
TSTF-11-15, Transmittal of TSTF-529, Revision 0, Clarify Use and Application RulesTechnical Specifications Task Force21 September 2011Transmittal of TSTF-529, Revision 0, Clarify Use and Application Rules
TSTF-11-13, Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition.Technical Specifications Task Force19 September 2011Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition.
TSTF-11-12, Transmittal of TSTF-530, Revision 0, Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09Technical Specifications Task Force16 September 2011Transmittal of TSTF-530, Revision 0, Clarify SR 3.0.3 to Be Consistent with Generic Letter 87-09
TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.Technical Specifications Task Force24 November 2010Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.
TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2Technical Specifications Task Force6 August 2010Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2
TSTF-10-10, Comment (1) of K. J. Schrader, D. W. Gregoire, T. W. Raidy & R. Gambrell on Behalf of Technical Specification Task Force on Proposed Model TSTF-514, Revision 1, Revise BWR Operability Requirements and Actions for RCS Leakage Instrument. (Technical Specifications Task Force12 May 2010Comment (1) of K. J. Schrader, D. W. Gregoire, T. W. Raidy & R. Gambrell on Behalf of Technical Specification Task Force on Proposed Model TSTF-514, Revision 1, Revise BWR Operability Requirements and Actions for RCS Leakage Instrument. (NR
TSTF-10-05, Transmittal of TSTF-523, Revision 0, Generic Letter 2008-01, Managing Gas AccumulationTechnical Specifications Task Force29 June 2010Transmittal of TSTF-523, Revision 0, Generic Letter 2008-01, Managing Gas Accumulation
TSTF-10-04, Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.Technical Specifications Task Force30 March 2010Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.
TSTF-09-25, Transmittal of Revised Risk-Informed End State Travelers: TSTF-422, TSTF-423, TSTF-431, and TSTF-432Technical Specifications Task Force22 December 2009Transmittal of Revised Risk-Informed End State Travelers: TSTF-422, TSTF-423, TSTF-431, and TSTF-432
TSTF-09-18, Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.Technical Specifications Task Force8 September 2009Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.
TSTF-09-03, Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage InstrumentationTechnical Specifications Task Force18 February 2009Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
TSTF-09-01, Transmittal of TSTF-515, Revision 0, Revise Post-Accident Monitoring Instrumentation Based on Reg. Guide 1.97, Rev. 4 and NEDO-33349.Technical Specifications Task Force20 January 2009Transmittal of TSTF-515, Revision 0, Revise Post-Accident Monitoring Instrumentation Based on Reg. Guide 1.97, Rev. 4 and NEDO-33349.
TSTF-08-20, Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.Technical Specifications Task Force10 November 2008Withdrawal of TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.
TSTF-08-18, Transmittal of TSTF-512, Revision 0, Revise SR 3.0.3 to Address SRs That Cannot Be Performed or Are Not Met.Technical Specifications Task Force14 October 2008Transmittal of TSTF-512, Revision 0, Revise SR 3.0.3 to Address SRs That Cannot Be Performed or Are Not Met.
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase StandardizationTechnical Specifications Task Force3 July 2008Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
TSTF-08-05, TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.Technical Specifications Task Force4 March 2008TSTF-506, Revision 0, Revise Primary Containment and Drywell Hydrogen Igniter Specification to Not Require Recombiners.
TSTF-08-04, TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).Technical Specifications Task Force19 February 2008TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
TSTF-07-27, Response to NRC Request for Additional Information Regarding TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461), Dated June 13, 2007Technical Specifications Task Force10 October 2007Response to NRC Request for Additional Information Regarding TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461), Dated June 13, 2007
TSTF-07-22, TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.Technical Specifications Task Force10 July 2007TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.
TSTF-07-14, TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions.Technical Specifications Task Force16 April 2007TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions.
TSTF-07-14, PROJ0753, TSTF-493, Revision 2, Clarity Application of Setpoint Methodology for LSSS FunctionsTechnical Specifications Task Force16 April 2007PROJ0753, TSTF-493, Revision 2, Clarity Application of Setpoint Methodology for LSSS Functions
TSTF-07-11, Revision to Implementation Guidance for TSTF-423, Technical Specifications End States, NEDC-32988-A.Technical Specifications Task Force9 March 2007Revision to Implementation Guidance for TSTF-423, Technical Specifications End States, NEDC-32988-A.
TSTF-07-09, TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.Technical Specifications Task Force21 February 2007TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.
TSTF-07-07, Response to NRC Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Dated November 9, 2006Technical Specifications Task Force7 February 2007Response to NRC Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Dated November 9, 2006
TSTF-07-04, TSTF-446, Revision 2, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).Technical Specifications Task Force11 January 2007TSTF-446, Revision 2, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
TSTF-06-28, TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461).Technical Specifications Task Force20 December 2006TSTF-498, Revision 0, Risk-Informed Containment Isolation Valve Completion Times (BAW-2461).
TSTF-06-20, TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03.18 July 2006TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03.
TSTF-05-17, TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A.19 September 2005TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A.
TSTF-05-15, TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)21 September 2005TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)
TSTF-05-14, TSTF-GG-05-01, Writer'S Guide for Plant-Specific Improved Technical Specifications30 June 2005TSTF-GG-05-01, Writer'S Guide for Plant-Specific Improved Technical Specifications
TSTF-05-14, TSTF-GG-05-01, Writer'S Guide for Plant Specific Improved Technical Specification, June 20059 August 2005TSTF-GG-05-01, Writer'S Guide for Plant Specific Improved Technical Specification, June 2005
TSTF-05-13, Technical Specification Task Force (TSTF) Response to May 25, 2005 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Re Revision to the Completion Time in STS 3.6.1.3, Primary Containment I25 July 2005Technical Specification Task Force (TSTF) Response to May 25, 2005 Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Re Revision to the Completion Time in STS 3.6.1.3, Primary Containment Iso
TSTF-05-13, Comment (1) of Paul Infanger, Michael Crowthers, Wesley Sparkman, & Brian Woods,On Behalf of Technical Specifications Task Force, Re Model Safety Evaluation on Technical Specification Improvement25 July 2005Comment (1) of Paul Infanger, Michael Crowthers, Wesley Sparkman, & Brian Woods,On Behalf of Technical Specifications Task Force, Re Model Safety Evaluation on Technical Specification Improvement
TSTF-05-12, TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability.18 August 2005TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability.
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity.29 June 2005Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity.
TSTF-05-06, TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities.5 May 2005TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities.
TSTF-04-15, TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a.2 December 2004TSTF-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a.
TSTF-04-12, Submittal and Request for Fee Waiver for Review of TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.25 April 2005Submittal and Request for Fee Waiver for Review of TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control.
TSTF-04-11, TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems30 August 2004TSTF-477, Revision 0, Add Action for Two Inoperable Control Room AC Subsystems
Regulatory Guide 7.931 March 1979Standard Format and Content of Part 71 Applications for Approval of Package of Type B, Large Quantity and Fissile Radioactive Material
Regulatory Guide 7.1030 June 2015(Draft Was Issued as DG-7009, Dated May 2013), Establishing Quality Assurance Programs for Packaging Used in Transport of Radioactive Material
Regulatory Guide 1.9631 May 1975Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants
Regulatory Guide 1.826 September 2005Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident
Regulatory Guide 1.7731 May 1974Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors
Regulatory Guide 1.730 September 1976Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident
Regulatory Guide 1.6831 January 1977Regulatory Guide 1.68.1, Revision 1, Preoperational and Initial Startup Testing of Feedwater and Condensate System for Boiling Water Reactor Power Plants
Regulatory Guide 1.5431 October 2010Service Level I, Ii, and Iii Protective Coatings Applied to Nuclear Power Plants
Regulatory Guide 1.5231 July 1976Design, Testing, and Maintenance Criteria for Engineered-safety-feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants
Regulatory Guide 1.3331 January 1977Quality Assurance Program Requirements (Operation)
Regulatory Guide 1.23227 February 2018Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors
Regulatory Guide 1.19531 May 2003Methods and Assumptions for Evaluating Radiological Consequences of Design-Basis Accidents at Light-Water Nuclear Power Reactors
Regulatory Guide 1.1941 June 2003Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants
Regulatory Guide 1.18928 February 2018Rev. 3, Fire Protection for Nuclear Power Plants
Regulatory Guide 1.15828 February 1989(Task Ee 006-5) Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants
Regulatory Guide 1.14031 August 2016Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
Regulatory Guide 1.12030 June 1976Fire Protection Guidelines for Nuclear Power Plants
Regulatory Guide 1.11730 June 1976Tornado Design Classification.
Regulatory Guide 1.1131 March 2010Instrument Lines Penetrating the Primary Reactor Containment
RS-18-113, Peach Bottom Atomic Power Station, Unit 2 - Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccidenPeach Bottom28 September 2018Peach Bottom Atomic Power Station, Unit 2 - Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident
RS-18-098, Peach Bottom Atomic Power Station, Units 2 and 3 - Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of InsightPeach Bottom28 August 2018Peach Bottom Atomic Power Station, Units 2 and 3 - Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights
RS-18-089, Quad Cities, Units 1 and 2 - Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EQuad Cities14 August 2018Quad Cities, Units 1 and 2 - Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA
RS-18-087, Quad Cities, Units 1 and 2 - Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Quad Cities14 August 2018Quad Cities, Units 1 and 2 - Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-18-059, Limerick, Unit 2, Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under SeverLimerick29 June 2018Limerick, Unit 2, Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe
RS-18-058, LaSalle County Station, Unit 2 - Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of OperatLaSalle22 June 2018LaSalle County Station, Unit 2 - Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operati
RS-18-030, Braidwood Station, Units 1 and 2 - Relief Requests Associated with the Fourth Inservice Inspection IntervalBraidwood19 March 2018Braidwood Station, Units 1 and 2 - Relief Requests Associated with the Fourth Inservice Inspection Interval
RS-18-022, Dresden Nuclear Power Station, Units 2 and 3, Response to NRC Request for Additional Information for Request for License Amendment to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program.Dresden14 February 2018Dresden Nuclear Power Station, Units 2 and 3, Response to NRC Request for Additional Information for Request for License Amendment to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program.
RS-18-006, Quad Cities, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.Quad Cities26 February 2018Quad Cities, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.
RS-18-005, Clinton Power Station, Unit 1 - License Amendment Request to Incorporate Revised Alternative Source Term Dose CalculationClinton9 January 2018Clinton Power Station, Unit 1 - License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation
RS-18-003, Dresden, Units 2 and 3, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident ConditionsDresden12 January 2018Dresden, Units 2 and 3, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
RS-18-002, Peach Bottom, Unit 3, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Peach Bottom5 January 2018Peach Bottom, Unit 3, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-18-001, Peach Bottom, Unit 3, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order NuPeach Bottom5 January 2018Peach Bottom, Unit 3, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Num
RS-17-164, Clinton, Unit 1, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.Clinton20 December 2017Clinton, Unit 1, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.
RS-17-162, LaSalle County Station, Units 1 and 2 - Exelon Nuclear Radiological Emergency Plan Addendum RevisionLaSalle15 November 2017LaSalle County Station, Units 1 and 2 - Exelon Nuclear Radiological Emergency Plan Addendum Revision
RS-17-157, Supplemental Information Regarding the Third Interval Containment Inservice Inspection (Cisi) Schedule for LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test IntervalsLaSalle8 November 2017Supplemental Information Regarding the Third Interval Containment Inservice Inspection (Cisi) Schedule for LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals
RS-17-155, Peach Bottom Atomic Power Station, Unit 2 - Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents CapabPeach Bottom15 December 2017Peach Bottom Atomic Power Station, Unit 2 - Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capabl
RS-17-153, Limerick Generating Station, Units 1 and 2 - Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents CapaLimerick15 December 2017Limerick Generating Station, Units 1 and 2 - Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capab
RS-17-145, Clinton, Unit 1 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory ControlClinton15 November 2017Clinton, Unit 1 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-17-133, Additional Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test IntervalsLaSalle3 October 2017Additional Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals
RS-17-131, Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test IntervalsLaSalle27 September 2017Supplemental Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals
RS-17-130, Quad Cities Nuclear Power Station, Units 1 and 2 - Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesQuad Cities28 September 2017Quad Cities Nuclear Power Station, Units 1 and 2 - Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-17-128, Byron, Units 1 and 2, Peach Bottom, Units 1, 2, and 3, Three Mile Island, Units 1 and 2 - Radiological Emergency Plan Annex and Addendum RevisionsPeach Bottom
Three Mile Island
Byron
07200068
21 September 2017Byron, Units 1 and 2, Peach Bottom, Units 1, 2, and 3, Three Mile Island, Units 1 and 2 - Radiological Emergency Plan Annex and Addendum Revisions
RS-17-127, LaSalle County Station, Units 1 and 2, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.LaSalle13 December 2017LaSalle County Station, Units 1 and 2, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements ManualQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary SystemsQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 8, Electric PowerQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 8, Electric Power
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and ControlsQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected SystemsQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient AnalysisQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 12, Radiation ProtectionQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of PlantQuad Cities19 October 2017Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-17-125, Byron, Units 1 and 2 - Relief Request RV-2 Associated with the Fourth Inservice Testing IntervalByron25 September 2017Byron, Units 1 and 2 - Relief Request RV-2 Associated with the Fourth Inservice Testing Interval
RS-17-111, Quad Cities, Units 1 and 2 - Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesQuad Cities27 July 2017Quad Cities, Units 1 and 2 - Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-17-099, Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch)LaSalle8 August 2017Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch)
RS-17-098, LaSalle, Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch)LaSalle17 July 2017LaSalle, Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch)
RS-17-096, Peach Bottom, Unit 3 - Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)Peach Bottom28 August 2017Peach Bottom, Unit 3 - Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)
RS-17-086, Dresden, Units 2 and 3 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.Dresden13 July 2017Dresden, Units 2 and 3 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.
RS-17-082, Dresden, Units 1, 2 and 3 - Updated Final Safety Analysis Report (Ufsar), Revision 12 and Fire Protection Report (Fpr), Amendment 21Dresden21 June 2017Dresden, Units 1, 2 and 3 - Updated Final Safety Analysis Report (Ufsar), Revision 12 and Fire Protection Report (Fpr), Amendment 21
RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 14, Initial Test ProgramDresden21 June 2017Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program
RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion SystemDresden21 June 2017Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
RS-17-079, Clinton, Unit 1 - Response to Request for Additional Information Regarding the Permanent Extension of Leak Rate TestingClinton1 June 2017Clinton, Unit 1 - Response to Request for Additional Information Regarding the Permanent Extension of Leak Rate Testing
RS-17-072, LaSalle County Station, Units 1 and 2 - Fourth 10-Year Interval Inservice Inspection Program Relief RequestsLaSalle30 May 2017LaSalle County Station, Units 1 and 2 - Fourth 10-Year Interval Inservice Inspection Program Relief Requests
RS-17-069, Quad Cities, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UQuad Cities27 June 2017Quad Cities, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Un
RS-17-067, Nine Mile Point, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of OperatiNine Mile Point30 June 2017Nine Mile Point, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operatio
RS-17-066, Limerick, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UndeLimerick30 June 2017Limerick, Units 1 and 2 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under
RS-17-063, Dresden, Units 2 and 3 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UnderDresden27 June 2017Dresden, Units 2 and 3 - Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under
RS-17-061, Quad Cities and R.E. Ginna - Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3Ginna
Quad Cities
07200067
3 May 2017Quad Cities and R.E. Ginna - Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3
RS-17-060, Dresden Nuclear Power Station, Unit 2 and 3 - Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (Cac. Nos. MF9687 and MF9688; EPID L-2017-LLA-0228) (RS-17-060)Dresden29 June 2018Dresden Nuclear Power Station, Unit 2 and 3 - Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (Cac. Nos. MF9687 and MF9688; EPID L-2017-LLA-0228) (RS-17-060)
RS-17-059, 10CFR50.54(q)(5) Procedure Change Summary Analysis, Rev. 27 to EP-AA-1003, Radiological Emergency Plan Annex and Rev. 28 to EP-AA-1000, Standardized Radiological Emergency Plan.Clinton26 April 201710CFR50.54(q)(5) Procedure Change Summary Analysis, Rev. 27 to EP-AA-1003, Radiological Emergency Plan Annex and Rev. 28 to EP-AA-1000, Standardized Radiological Emergency Plan.
RS-17-051, Quad Cities Nuclear Power Station, Units 1 and 2 - Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MF9675, and MF9676, EPID L-2017-LLA-0220)Quad Cities1 December 2017Quad Cities Nuclear Power Station, Units 1 and 2 - Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MF9675, and MF9676, EPID L-2017-LLA-0220)
RS-17-049, Exelon Generation Co., LLC - Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement ProcessNine Mile Point
Dresden
Ginna
Quad Cities
Peach Bottom
Three Mile Island
Calvert Cliffs
Limerick
LaSalle
Byron
Braidwood
Clinton
28 March 2017Exelon Generation Co., LLC - Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process
RS-17-029, Dresden Nuclear Power Station, Unit 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.Dresden10 February 2017Dresden Nuclear Power Station, Unit 2 and 3 - Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.
RS-17-024, LaSalle, Units 1 & 2 - Supplement to License Amendment Request for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Regarding Hardened Containment Vent System Modifications and Installation of Primary Containment IsolatiLaSalle16 February 2017LaSalle, Units 1 & 2 - Supplement to License Amendment Request for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Regarding Hardened Containment Vent System Modifications and Installation of Primary Containment Isolatio
RS-17-021, Peach Bottom, Unit 3 - Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External EventsPeach Bottom28 February 2017Peach Bottom, Unit 3 - Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events
RS-17-020, Clinton, Unit 1 - Response to RAI Concerning License Amendment Request to Revise Technical Specification Section 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test FrequencClinton2 March 2017Clinton, Unit 1 - Response to RAI Concerning License Amendment Request to Revise Technical Specification Section 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequenci
RS-17-017, Clinton, Unit 1 - License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal OperationsClinton4 May 2017Clinton, Unit 1 - License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations
RS-17-008, Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident.Quad Cities26 January 2017Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident.
RS-17-006, Request for Extension to Comply with NRC Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions and NRC Order EA-12-049, Order Modifying Licenses WQuad Cities12 January 2017Request for Extension to Comply with NRC Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions and NRC Order EA-12-049, Order Modifying Licenses Wi
RS-16-257, Quad Cities Nuclear Power Station Unit 1 and 2, Withdrawal of Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesQuad Cities22 December 2016Quad Cities Nuclear Power Station Unit 1 and 2, Withdrawal of Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-16-254, Quad Cities, Units 1 and 2 - Supplemental Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesQuad Cities15 December 2016Quad Cities, Units 1 and 2 - Supplemental Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-16-251, Clinton Power Station, Unit 1, Request to Resume Review of Licensing ActionsClinton15 December 2016Clinton Power Station, Unit 1, Request to Resume Review of Licensing Actions
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 14, Initial Test ProgramByron
Braidwood
07200068
07200073
15 December 2016Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory GuidesByron
Braidwood
07200068
07200073
15 December 2016Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements ManualByron
Braidwood
07200068
07200073
15 December 2016Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
RS-16-245, Exelon Nuclear Radiological Emergency Plan RevisionsNine Mile Point
Quad Cities
07201036
Dresden
9 December 2016Exelon Nuclear Radiological Emergency Plan Revisions
RS-16-244, Dresden, Units 2 and 3, LaSalle County, Units 1 and 2, Quad Cities, Units 1 and 2 - Additional Information Regarding Request for License Amendment to Address Secondary Containment Access OpeningsDresden
Quad Cities
LaSalle
12 December 2016Dresden, Units 2 and 3, LaSalle County, Units 1 and 2, Quad Cities, Units 1 and 2 - Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings
RS-16-236, Nine Mile Point, Units 1 & 2 - Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable Operation UnNine Mile Point14 December 2016Nine Mile Point, Units 1 & 2 - Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable Operation Und
RS-16-234, Limerick Generating Station, Units 1 and 2 - Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents CapablLimerick15 December 2016Limerick Generating Station, Units 1 and 2 - Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable
RS-16-233, LaSalle County, Unit 1 & 2 - Fifth Six-Month Status Report for Phases 1&2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UnderLaSalle14 December 2016LaSalle County, Unit 1 & 2 - Fifth Six-Month Status Report for Phases 1&2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under.
RS-16-228, Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ConditionClinton17 November 2016Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-16-217, Braidwood Station Units 1 & 2, Clinton Power Station Unit 1, LaSalle County Station Units 1 & 2, and Nine Mile Point Nuclear Station Unit 1, Exelon Nuclear Radiological Emergency Plan Addendum RevisionsNine Mile Point
Braidwood
Clinton
07200073
07201036
LaSalle
25 October 2016Braidwood Station Units 1 & 2, Clinton Power Station Unit 1, LaSalle County Station Units 1 & 2, and Nine Mile Point Nuclear Station Unit 1, Exelon Nuclear Radiological Emergency Plan Addendum Revisions
RS-16-210, Request for Extension to Comply with NRC Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions and NRC Order EA-12-049, Order Modifying Licenses wQuad Cities16 November 2016Request for Extension to Comply with NRC Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions and NRC Order EA-12-049, Order Modifying Licenses wi
RS-16-208, Clinton, Unit 1 - Response to NRC Acknowledgement of Suspension Request for Licensing ActionsClinton1 November 2016Clinton, Unit 1 - Response to NRC Acknowledgement of Suspension Request for Licensing Actions
RS-16-205, LaSalle County Station, Units 1 and 2 - Relief Requests Associated with the Fourth Interval Inservice Testing ProgramLaSalle17 October 2016LaSalle County Station, Units 1 and 2 - Relief Requests Associated with the Fourth Interval Inservice Testing Program
RS-16-196, Redacted Clinton - Updated Safety Analysis Report (Usar), Revision 18, Appendix D - Requirements Resulting from TIM-2 AccidentClinton31 October 2016Redacted Clinton - Updated Safety Analysis Report (Usar), Revision 18, Appendix D - Requirements Resulting from TIM-2 Accident
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 9 - Auxiliary SystemsClinton31 October 2016Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 9 - Auxiliary Systems
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected SystemsClinton31 October 2016Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 14 - Initial Test ProgramClinton31 October 2016Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 14 - Initial Test Program
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Appendix a - GlossaryClinton31 October 2016Clinton - Updated Safety Analysis Report (Usar), Revision 18, Appendix a - Glossary
RS-16-191, LaSalle County Station Units 1 & 2 - License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesLaSalle26 October 2016LaSalle County Station Units 1 & 2 - License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-16-187, Quad Cities, Units 1 and 2 - Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesQuad Cities19 September 2016Quad Cities, Units 1 and 2 - Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
RS-16-182, LaSalle County Station, Units 1 and 2 - Mitigating Strategies Flood Hazard Assessment (Msfha) SubmittalLaSalle28 October 2016LaSalle County Station, Units 1 and 2 - Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
RS-16-176, LaSalle County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the FukushimLaSalle1 December 2016LaSalle County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima
RS-16-161, Clinton, Unit 1 - Request for NRC to Suspend Review of License Amendment RequestsClinton11 August 2016Clinton, Unit 1 - Request for NRC to Suspend Review of License Amendment Requests
RS-16-149, Peach Bottom, Units 2 and 3 - Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-Peach Bottom26 August 2016Peach Bottom, Units 2 and 3 - Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-1
RS-16-143, Attachments 1 - 7: Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled ConditionClinton11 August 2016Attachments 1 - 7: Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition
RS-16-111, Nine Mile Point, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/13 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccidNine Mile Point30 June 2016Nine Mile Point, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/13 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accide
RS-16-110, Quad Cities, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccidenQuad Cities30 June 2016Quad Cities, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident
RS-16-109, Peach Bottom, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 6/6/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccidentPeach Bottom30 June 2016Peach Bottom, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 6/6/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident
RS-16-108, Limerick, Fourth Six Month Status Report for Phases 1 & 2 Integrated Plan in Response to 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident ConditionLimerick30 June 2016Limerick, Fourth Six Month Status Report for Phases 1 & 2 Integrated Plan in Response to 06/06/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
RS-16-107, LaSalle County, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/13 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccideLaSalle30 June 2016LaSalle County, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 06/06/13 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Acciden
RS-16-106, Dresden, Units 2 and 3 - Fourth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UndeDresden30 June 2016Dresden, Units 2 and 3 - Fourth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under
RS-16-090, Dresden Nuclear Power Station Unit 3 - Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049Dresden16 August 2016Dresden Nuclear Power Station Unit 3 - Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-16-089, Nine Mile Point Nuclear Station, Unit 2 - Final Integrated Plan Document- Mitigating Strategies NRC Order EA-12-049Nine Mile Point1 July 2016Nine Mile Point Nuclear Station, Unit 2 - Final Integrated Plan Document- Mitigating Strategies NRC Order EA-12-049
RS-16-080, LaSalle County, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 22, List of Effective Pages11 April 2016LaSalle County, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 22, List of Effective Pages
RS-16-080, LaSalle County, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 22, Chapter 1.0 - Introduction and General Description of Plant11 April 2016LaSalle County, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 22, Chapter 1.0 - Introduction and General Description of Plant
RS-16-080, LaSalle County, Units 1 and 2 - Transmittal of Updated Final Safety Analysis Report (Ufsar), Revision 22 and Fire Protection Report (Fpr), Revision 7LaSalle11 April 2016LaSalle County, Units 1 and 2 - Transmittal of Updated Final Safety Analysis Report (Ufsar), Revision 22 and Fire Protection Report (Fpr), Revision 7
RS-16-068, LaSalle County, Units 1 and 2 - Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal ApplicationLaSalle4 April 2016LaSalle County, Units 1 and 2 - Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application
RS-16-035, Dresden, LaSalle County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access OpeningsDresden
Quad Cities
LaSalle
3 February 2016Dresden, LaSalle County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings
RS-16-029, Nine Mile Point, Unit 2 - Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049Nine Mile Point26 February 2016Nine Mile Point, Unit 2 - Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-16-026, Peach Bottom, Units 1 and 2 - Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12Peach Bottom26 February 2016Peach Bottom, Units 1 and 2 - Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-
RS-16-019, Clinton, Unit 1 - License Amendment Request to Incorporate Revised Alternative Source Term Dose CalculationClinton29 January 2016Clinton, Unit 1 - License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation
RS-16-019, Clinton Power Station, Unit No. 1 - Issuance of Amendment Concerning Incorporation of Revised Alternative Source Term (CAC No. MF7336) (RS-16-019)Clinton17 August 2016Clinton Power Station, Unit No. 1 - Issuance of Amendment Concerning Incorporation of Revised Alternative Source Term (CAC No. MF7336) (RS-16-019)
RS-15-320, Clinton, Unit 1 - Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049Clinton14 December 2015Clinton, Unit 1 - Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049
RS-15-305, LaSalle County, Units 1 and 2 - Corrections to the License Renewal Application Dated December 9, 2014LaSalle2 December 2015LaSalle County, Units 1 and 2 - Corrections to the License Renewal Application Dated December 9, 2014
RS-15-304, Quad Cities, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccidenQuad Cities16 December 2015Quad Cities, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident
RS-15-303, Peach Bottom, Units 2 & 3 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccidentPeach Bottom15 December 2015Peach Bottom, Units 2 & 3 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident
RS-15-302, Nine Mile Point, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AccNine Mile Point15 December 2015Nine Mile Point, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Acci
RS-15-301, Limerick, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident CLimerick15 December 2015Limerick, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Co
RS-15-300, LaSalle County, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe AcciLaSalle16 December 2015LaSalle County, Units 1 and 2 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accid
RS-15-299, Dresden, Units 2 and 3 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident CoDresden16 December 2015Dresden, Units 2 and 3 - Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Con
RS-15-253, Byron Station, Units 1 and 2 - Withdrawal of Relief Request RV-1 and Revision to Relief Request RG-1 Associated with the Fourth Inservice Testing IntervalByron21 September 2015Byron Station, Units 1 and 2 - Withdrawal of Relief Request RV-1 and Revision to Relief Request RG-1 Associated with the Fourth Inservice Testing Interval
RS-15-246, Clinton Power Station Unit 1 Exigent License Amendment Request for One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion TimeClinton10 September 2015Clinton Power Station Unit 1 Exigent License Amendment Request for One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time
RS-15-239, LaSalle County, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 8, Dated August 28, 2015 Related to the License Renewal ApplicationLaSalle28 September 2015LaSalle County, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 8, Dated August 28, 2015 Related to the License Renewal Application
RS-15-237, Attachment 12 - ANP-3328NP, Revision 1, Quad Cities Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel. (Non-Proprietary)Dresden
Quad Cities
31 August 2015Attachment 12 - ANP-3328NP, Revision 1, Quad Cities Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel. (Non-Proprietary)
RS-15-223, LaSalle County, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 7, Dated July 27, 2015; and a Correction to Information Associated with the Set 2 Response to RAI 8.2.1.20-2, Related to the Renewal ApplicationLaSalle26 August 2015LaSalle County, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 7, Dated July 27, 2015; and a Correction to Information Associated with the Set 2 Response to RAI 8.2.1.20-2, Related to the Renewal Application
RS-15-219, Nine Mile Point, Unit 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049Nine Mile Point28 August 2015Nine Mile Point, Unit 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-15-215, Quad Cities Nuclear Power Station, Units 1 and 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External EventQuad Cities28 August 2015Quad Cities Nuclear Power Station, Units 1 and 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RS-15-214, Peach Bottom, Units 2 and 3 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12Peach Bottom28 August 2015Peach Bottom, Units 2 and 3 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-
RS-15-212, Limerick Generating Station, Units 1 and 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.Limerick28 August 2015Limerick Generating Station, Units 1 and 2 - Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.
RS-15-180, LaSalle County, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 4, Dated June 19, 2015 Related to the License Renewal ApplicationLaSalle15 July 2015LaSalle County, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 4, Dated June 19, 2015 Related to the License Renewal Application
RS-15-170, Byron Station, Units 1 and 2 - Submittal of Relief Requests Associated with the Fourth Inservice Testing IntervalByron22 June 2015Byron Station, Units 1 and 2 - Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval
RS-15-153, Nine Mile Point, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UndNine Mile Point30 June 2015Nine Mile Point, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Unde
RS-15-152, Quad Cities, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under SQuad Cities30 June 2015Quad Cities, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Se
RS-15-150, Limerick, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under SeveLimerick30 June 2015Limerick, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Sever
RS-15-149, LaSalle County, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation UndeLaSalle30 June 2015LaSalle County, Units 1 and 2 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under
RS-15-148, Dresden, Units 2 and 3 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under SeverDresden30 June 2015Dresden, Units 2 and 3 - Second Six-Month Status Report for Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe
RS-15-138, Clinton, Unit 1 - Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Clinton15 July 2015Clinton, Unit 1 - Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-15-101, Limerick, Unit 2 - Request for Schedule Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.Limerick2 April 2015Limerick, Unit 2 - Request for Schedule Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.
RS-15-088, Quad Cities, Unit 1 - Request for Schedule Relaxation from NRC Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Bases External EventsQuad Cities4 March 2015Quad Cities, Unit 1 - Request for Schedule Relaxation from NRC Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Bases External Events
RS-15-086, Nine Mile Point, Unit 2 - Partial Withdrawal of Request for Exemption from 10 CFR 50, Appendix a, GDC-56 - Penetration Z-48 (Drywell)Nine Mile Point30 March 2015Nine Mile Point, Unit 2 - Partial Withdrawal of Request for Exemption from 10 CFR 50, Appendix a, GDC-56 - Penetration Z-48 (Drywell)
RS-15-082, Attachment 10 - EP-AA-1006, Revised Radiological Emergency Plan Annex Information for Quad Cities Nuclear StationQuad Cities2 March 2015Attachment 10 - EP-AA-1006, Revised Radiological Emergency Plan Annex Information for Quad Cities Nuclear Station
RS-15-071, Braidwood, Units 1 & 2 and Byron, Units 1 & 2, Response to NRC Request for Additional Information, Set 45, Dated January 22, 2015, Related to License Renewal ApplicationByron
Braidwood
23 February 2015Braidwood, Units 1 & 2 and Byron, Units 1 & 2, Response to NRC Request for Additional Information, Set 45, Dated January 22, 2015, Related to License Renewal Application
RS-15-057, Nine Mile Point, Units 1 & 2 - February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order NumNine Mile Point19 February 2015Nine Mile Point, Units 1 & 2 - February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Numb
RS-15-038, Limerick, Unit 2, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentLimerick31 March 2015Limerick, Unit 2, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
RS-15-024, Quad Cities, Units 1 and 2, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-Quad Cities27 February 2015Quad Cities, Units 1 and 2, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-0
RS-15-018, Clinton, Unit 1 - Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Clinton27 February 2015Clinton, Unit 1 - Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-15-016, LaSalle, Units 1 and 2 - Response to NRC Request for Additional Information, Set 1, Dated May 14, 2015 Related to the License Renewal Application (TAC Nos. MF5347 and MF5346)LaSalle8 June 2015LaSalle, Units 1 and 2 - Response to NRC Request for Additional Information, Set 1, Dated May 14, 2015 Related to the License Renewal Application (TAC Nos. MF5347 and MF5346)
RS-14-348, Braidwood, Units 1 and 2, Byron, Units 1 and 2, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal ApplicationByron
Braidwood
15 December 2014Braidwood, Units 1 and 2, Byron, Units 1 and 2, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application
RS-14-338, Byron, Units 1 and 2, and Braidwood, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26, Revision 15, Chapter 6 - Engineered Safety FeaturesByron
Braidwood
07200068
07200073
15 December 2014Byron, Units 1 and 2, and Braidwood, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26, Revision 15, Chapter 6 - Engineered Safety Features
RS-14-338, Byron, Units 1 and 2, and Braidwood, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26, Chapter 14 - Initial Test ProgramByron
Braidwood
07200068
07200073
15 December 2014Byron, Units 1 and 2, and Braidwood, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26, Chapter 14 - Initial Test Program
RS-14-322, Dresden, Units 2 & 3, LaSalle, Units 1 & 2 and Quad Cities, Units 1 & 2 - License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use ODresden
Quad Cities
LaSalle
22 December 2014Dresden, Units 2 & 3, LaSalle, Units 1 & 2 and Quad Cities, Units 1 & 2 - License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of
RS-14-218, Braidwood, Units 1 and 2, and Byron, Units 1 and 2, Responses to NRC Requests for Additional Information, Sets 33 and 34, Both Dated June 23, 2014; and Corrections and Clarifications Related to the License Renewal ApplicationByron
Braidwood
18 July 2014Braidwood, Units 1 and 2, and Byron, Units 1 and 2, Responses to NRC Requests for Additional Information, Sets 33 and 34, Both Dated June 23, 2014; and Corrections and Clarifications Related to the License Renewal Application
RS-14-192, Exelon Generation - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement ProcessDresden
Quad Cities
LaSalle
Byron
Braidwood
Clinton
14 July 2014Exelon Generation - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process
RS-14-162, Braidwood, Units 1 & 2, Byron, Units 1 & 2, Corrections to the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal ApplicationByron
Braidwood
23 May 2014Braidwood, Units 1 & 2, Byron, Units 1 & 2, Corrections to the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Technical Specifications BasesLaSalle11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Technical Specifications Bases
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Table of Contents and List of Effective Pages11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Table of Contents and List of Effective Pages
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 9.0, Auxiliary SystemsLaSalle11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 9.0, Auxiliary Systems
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 8.0, Electric Power11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 8.0, Electric Power
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 6.0, Engineered Safety FeaturesLaSalle11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 6.0, Engineered Safety Features
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 5.0, Reactor Coolant System and Connected Systems11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 5.0, Reactor Coolant System and Connected Systems
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 15.0, Accident AnalysesLaSalle11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 15.0, Accident Analyses
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 1.0, Introduction and General Description of Plant11 April 2014LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 1.0, Introduction and General Description of Plant
RS-14-127, LaSalle, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Revise Peak Calculated Primary Containment Internal PressureLaSalle12 June 2014LaSalle, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure
RS-14-126, Response to NRC Request for Additional Information, Set 20, Dated April 7, 2014, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1, and 2, License Renewal ApplicationByron
Braidwood
6 May 2014Response to NRC Request for Additional Information, Set 20, Dated April 7, 2014, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1, and 2, License Renewal Application
RS-14-115, Attachment 6: Discussion of Revision to the Radiological Emergency Plan Annex for LaSalle County Station. LS 3-75 Through LS 3-150LaSalle30 May 2014Attachment 6: Discussion of Revision to the Radiological Emergency Plan Annex for LaSalle County Station. LS 3-75 Through LS 3-150
RS-14-115, Attachment 10: Discussion of Revision to the Radiological Emergency Plan Annex for Quad Cities Nuclear Power Station, Page QC 3-69 Through EndQuad Cities30 May 2014Attachment 10: Discussion of Revision to the Radiological Emergency Plan Annex for Quad Cities Nuclear Power Station, Page QC 3-69 Through End
RS-14-097, Braidwood and Byron, Units 1 & 2 - Responses to NRC Requests for Additional Information, Set 14, Dated March 18, 2014, Related to License Renewal ApplicationByron
Braidwood
17 April 2014Braidwood and Byron, Units 1 & 2 - Responses to NRC Requests for Additional Information, Set 14, Dated March 18, 2014, Related to License Renewal Application
RS-14-063, Quad Cities, Units 1 and 2 - Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses Re Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)Quad Cities30 June 2014Quad Cities, Units 1 and 2 - Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses Re Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
RS-14-062, Peach Bottom, Units 2 & 3, Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order NumbPeach Bottom30 June 2014Peach Bottom, Units 2 & 3, Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Numbe
RS-14-060, Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)Limerick30 June 2014Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
RS-14-059, LaSalle, Units 1 and 2 - Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order NumberLaSalle30 June 2014LaSalle, Units 1 and 2 - Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number
RS-14-058, Dresden, Units 2 and 3 - Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order NumberDresden30 June 2014Dresden, Units 2 and 3 - Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number
RS-14-047, Peach Bottom Atomic Power Station, Unit 3 - Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External EventsPeach Bottom26 February 2014Peach Bottom Atomic Power Station, Unit 3 - Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RS-14-046, Quad Cities, Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External EventsQuad Cities27 February 2014Quad Cities, Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RS-14-045, LaSalle County Station, Units 1 and 2 - Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External EventsLaSalle27 February 2014LaSalle County Station, Units 1 and 2 - Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RS-14-015, Quad Cities, Units 1 and 2, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order No. EA-12-049Quad Cities28 February 2014Quad Cities, Units 1 and 2, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order No. EA-12-049)
RS-14-009, Clinton, Unit 1, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order No. EA-12-049)Clinton28 February 2014Clinton, Unit 1, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order No. EA-12-049)
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 9 - Auxiliary SystemsClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 9 - Auxiliary Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 7 - Instrument and Control SystemsClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 7 - Instrument and Control Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected SystemsClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and SystemsClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 15 - Accident AnalysisClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 15 - Accident Analysis
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 14 - Initial Test ProgramClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 14 - Initial Test Program
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of PlantClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Appendix a - GlossaryClinton9 January 2014Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Appendix a - Glossary
RS-14-003, Braidwood, Units 1 and 2, and Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal ApplicationByron
Braidwood
13 January 2014Braidwood, Units 1 and 2, and Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application
RS-13-288, Dresden, Units 2 and 3 and Quad Cities, Units 1 and 2, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.Dresden
Quad Cities
19 December 2013Dresden, Units 2 and 3 and Quad Cities, Units 1 and 2, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.
RS-13-240, Braidwood Station Units 1 & 2, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.Braidwood10 October 2013Braidwood Station Units 1 & 2, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.
RS-13-138, Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138Limerick7 October 2013Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138
RS-13-136, Quad Cities, Unit 1, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentQuad Cities27 June 2013Quad Cities, Unit 1, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
RS-13-119, Dresden, Units 2 and 3, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Dresden28 August 2013Dresden, Units 2 and 3, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-13-117, Clinton, Unit 1 - First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Clinton28 August 2013Clinton, Unit 1 - First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-13-111, Dresden Nuclear Power Station, Units 2 and 3, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Hardened Containment Vents (Order Number EA-12-050)Dresden28 February 2013Dresden Nuclear Power Station, Units 2 and 3, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Hardened Containment Vents (Order Number EA-12-050)
RS-13-092, LaSalle, Units 1 and 2, License Amendment Request to Revise Peak Calculated Primary Containment Internal PressureLaSalle5 September 2013LaSalle, Units 1 and 2, License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure
RS-13-085, Peach Bottom, Units 2 and 3, Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, EmergenPeach Bottom30 April 2013Peach Bottom, Units 2 and 3, Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergenc
RS-13-084, Limerick, Units 1 and 2, Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, EmergenLimerick30 April 2013Limerick, Units 1 and 2, Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergenc
RS-13-062, Quad Cities, Units 1 and 2, Fifth Ten-Year Interval Inservice Testing ProgramQuad Cities25 February 2013Quad Cities, Units 1 and 2, Fifth Ten-Year Interval Inservice Testing Program
RS-13-052, Clinton, Unit 1, Additional Information Regarding Relief Request I3R-09, Alternative to VT-2 Visual Inspection of Combustible Gas Control System PipingClinton8 February 2013Clinton, Unit 1, Additional Information Regarding Relief Request I3R-09, Alternative to VT-2 Visual Inspection of Combustible Gas Control System Piping
RS-13-024, Peach Bottom Atomic Power Station, Units 2 & 3 - Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12Peach Bottom28 February 2013Peach Bottom Atomic Power Station, Units 2 & 3 - Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-
RS-13-023, Oyster Creek, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Oyster Creek28 February 2013Oyster Creek, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-13-022, Limerick, Units 1 & 2 - Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)Limerick28 February 2013Limerick, Units 1 & 2 - Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 9 - Auxiliary SystemsClinton10 January 2013Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 9 - Auxiliary Systems
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 7 - Instrumentation and Control SystemsClinton10 January 2013Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 7 - Instrumentation and Control Systems
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected SystemsClinton10 January 2013Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and SystemsClinton10 January 2013Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems
RS-13-002, LaSalle County Station, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Technical Specification 3.7.3, Ultimate Heat Sink.LaSalle18 January 2013LaSalle County Station, Units 1 and 2, Response to Request for Additional Information Related to License Amendment Request to Technical Specification 3.7.3, Ultimate Heat Sink.
RS-12-223, Braidwood Station, Units 1 & 2 and Byron Station, Units 1 & 2, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation.Byron
Braidwood
21 December 2012Braidwood Station, Units 1 & 2 and Byron Station, Units 1 & 2, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation.
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications BasesByron
07200068
14 December 2012Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements ManualByron
07200068
14 December 2012Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications BasesBraidwood
07200073
14 December 2012Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 9.0 - Auxiliary SystemsByron
Braidwood
07200073
07200068
14 December 2012Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 9.0 - Auxiliary Systems
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 7.0 - Instrumentation and ControlsByron
Braidwood
07200073
07200068
14 December 2012Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 7.0 - Instrumentation and Controls
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 6.0 - Engineered Safety FeaturesByron
Braidwood
07200073
07200068
14 December 2012Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 6.0 - Engineered Safety Features
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 14.0 - Initial Test ProgramBraidwood
Byron
07200068
07200073
14 December 2012Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 14.0 - Initial Test Program
RS-12-179, Quad Cities, Units 1 and 2 - Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing IntervalQuad Cities8 October 2012Quad Cities, Units 1 and 2 - Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval
RS-12-174, Exelon Generation Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AcPeach Bottom19 November 2012Exelon Generation Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc
RS-12-156, Exelon Generation Company, LLC 90-Day Response to NRC Bulletin 2012-01, Design Vulnerability in Electric Power SystemOyster Creek
Dresden
Quad Cities
Peach Bottom
Three Mile Island
Limerick
LaSalle
Byron
Braidwood
Clinton
25 October 2012Exelon Generation Company, LLC 90-Day Response to NRC Bulletin 2012-01, Design Vulnerability in Electric Power System
RS-12-155, Dresden, Units 2 and 3 - Submittal of Relief Requests Associated with the Fifth Lnservice Testing IntervalDresden30 October 2012Dresden, Units 2 and 3 - Submittal of Relief Requests Associated with the Fifth Lnservice Testing Interval
RS-12-154, Attachment D to Proto-Power Calculation 97-195, Revision aLaSalle17 September 2012Attachment D to Proto-Power Calculation 97-195, Revision a
RS-12-154, Attachment 6 - LaSalle County Station Engineering Change (EC) 388666, Revision 0, Revise Design Analyses for UHS Temperature of 107 'FLaSalle17 September 2012Attachment 6 - LaSalle County Station Engineering Change (EC) 388666, Revision 0, Revise Design Analyses for UHS Temperature of 107 'F
RS-12-154, Attachment 2 - Heat Transfer Calculations Used to Develop Attachment 5 and Table A5-1 in the July 12, 2012, License Amendment RequestLaSalle17 September 2012Attachment 2 - Heat Transfer Calculations Used to Develop Attachment 5 and Table A5-1 in the July 12, 2012, License Amendment Request
RS-12-150, Quad Cities, Units 1 and 2, Fifth Interval Inservice Inspection Program Plan and Relief RequestsQuad Cities28 September 2012Quad Cities, Units 1 and 2, Fifth Interval Inservice Inspection Program Plan and Relief Requests
RS-12-149, Quad Cities, Units 1 and 2, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing IntervalQuad Cities13 September 2012Quad Cities, Units 1 and 2, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval
RS-12-026, Quad Cities, Units 1 and 2- Submittal of Relief Requests Associated with the Fifth Inservice Testing IntervalQuad Cities15 February 2012Quad Cities, Units 1 and 2- Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient AnalysesQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 12 - Radiation ProtectionQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 12 - Radiation Protection
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 11 - Radioactive Waste ManagementQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 11 - Radioactive Waste Management
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 07 - Instrumentation and ControlsQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 07 - Instrumentation and Controls
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected SystemsQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 01 - IntroductionQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 01 - Introduction
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix aQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a
RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification BasesQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Technical Specification Bases
RS-11-159, Quad Cities, Units 1 and 2 - Technical Requirements ManualQuad Cities19 October 2011Quad Cities, Units 1 and 2 - Technical Requirements Manual
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification BasesDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 9.0, Auxiliary SystemsDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 9.0, Auxiliary Systems
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 7.0, Instrumentation and ControlsDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 7.0, Instrumentation and Controls
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 6.0, Engineered Safety FeaturesDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 6.0, Engineered Safety Features
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected SystemsDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected Systems
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 14.0, Initial Test ProgramDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 14.0, Initial Test Program
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 12.0, Radiation Protection, Beginning Through Table 12A-4(1)Dresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 12.0, Radiation Protection, Beginning Through Table 12A-4(1)
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 10.0, Steam and Power Conversion SystemDresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 10.0, Steam and Power Conversion System
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9Dresden29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9
RS-10-208, Dresden, Units 2 and 3 - Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation InstrumentationDresden13 December 2010Dresden, Units 2 and 3 - Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
RS-10-172, Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2 - Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.Dresden
Quad Cities
12 October 2010Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2 - Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.
RS-10-152, Dresden Nuclear Power Station, Units 2 & 3 - Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation InstrumentationDresden15 September 2010Dresden Nuclear Power Station, Units 2 & 3 - Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
RS-10-096, Quad Cities, Units 1 & 2 - Supplemental Information Concerning Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection InstrumentationQuad Cities2 June 2010Quad Cities, Units 1 & 2 - Supplemental Information Concerning Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation
RS-10-093, Clinton, Unit 1, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5BClinton21 May 2010Clinton, Unit 1, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B
RS-10-039, Clinton, Unit 1, License Amendment Request to Administratively Revise Technical SpecificationsClinton4 June 2010Clinton, Unit 1, License Amendment Request to Administratively Revise Technical Specifications
RS-10-032, Quad Cities, Units 1 and 2 - Application for Technical Specification Change Regarding Risk-informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, ReQuad Cities16 February 2010Quad Cities, Units 1 and 2 - Application for Technical Specification Change Regarding Risk-informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev
RS-10-031, LaSalle County Station, Units 1 and 2, Application for Technical Specification Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-4LaSalle15 February 2010LaSalle County Station, Units 1 and 2, Application for Technical Specification Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-42
RS-10-029, Braidwood, Units 1 & 2, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled ProgramBraidwood15 February 2010Braidwood, Units 1 & 2, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program
RS-10-028, Clinton, Unit 1, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.Dresden
Quad Cities
Clinton
3 March 2010Clinton, Unit 1, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.
RS-10-024, Dresden, Units 2 & 3, Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled ProgramDresden16 February 2010Dresden, Units 2 & 3, Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program
RS-10-018, Dresden Nuclear Power Station, Units 2 and 3, Request for License Amendment Regarding Shutdown Cooling System Isolation InstrumentationDresden4 February 2010Dresden Nuclear Power Station, Units 2 and 3, Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
RS-10-015, LaSalle County, Units 1 and 2, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.LaSalle22 February 2010LaSalle County, Units 1 and 2, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.
RS-10-001, LaSalle, Units 1 and 2, Attachment 8 - NEDO-33485, Rev. 0, Safety Analysis Report for LaSalle County Station Units 1 and 2, Thermal Power Optimization.LaSalle27 January 2010LaSalle, Units 1 and 2, Attachment 8 - NEDO-33485, Rev. 0, Safety Analysis Report for LaSalle County Station Units 1 and 2, Thermal Power Optimization.
RS-09-153, Peach Bottom, Units 2 and 3, Response to Request for Additional Information Regarding Generic Letter 2008-01Peach Bottom10 November 2009Peach Bottom, Units 2 and 3, Response to Request for Additional Information Regarding Generic Letter 2008-01
RS-09-152, Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2 - Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) SystemDresden
Quad Cities
10 November 2009Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2 - Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System
RS-09-135, LaSalle, Units 1 and 2 - Additional Information Supporting the License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating.LaSalle28 October 2009LaSalle, Units 1 and 2 - Additional Information Supporting the License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating.
RS-09-130, LaSalle, Units 1 & 2 - Additional Information Supporting Request for License Amendment Regarding Application of Alternative Source TermLaSalle28 September 2009LaSalle, Units 1 & 2 - Additional Information Supporting Request for License Amendment Regarding Application of Alternative Source Term
RS-09-118, Braidwood Station, Units 1 & 2 - Submittal of Relief Requests Associated with the Third Inservice Inspection IntervalBraidwood4 September 2009Braidwood Station, Units 1 & 2 - Submittal of Relief Requests Associated with the Third Inservice Inspection Interval
RS-09-114, LaSalle County Station Units 1 & 2, Site-Specific Safstor Decommissioning Cost EstimateLaSalle27 August 2009LaSalle County Station Units 1 & 2, Site-Specific Safstor Decommissioning Cost Estimate
RS-09-105, Clinton, Unit 1, Withdrawal of Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building TClinton4 August 2009Clinton, Unit 1, Withdrawal of Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building Te
RS-09-104, Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2 - Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell LeakageDresden
Quad Cities
28 August 2009Dresden, Units 2 & 3 and Quad Cities, Units 1 & 2 - Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage
RS-09-078, Clinton, Unit 1 - Response to Request for Additional Information Related to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation InstrumentationClinton23 June 2009Clinton, Unit 1 - Response to Request for Additional Information Related to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
RS-09-077, Clinton, Unit 1 - Request for Processing an Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building.Clinton20 June 2009Clinton, Unit 1 - Request for Processing an Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building..
RS-09-020, LaSalle, Units 1 and 2, Request for a License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating.LaSalle26 March 2009LaSalle, Units 1 and 2, Request for a License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating.
RS-09-003, Clinton, Unit 1, Dresden, Units 2 & 3 and Quad Cities Units 1 & 2 - Additional Information Supporting Requests for License Amendments to Adopt TSTF-423, Technical Specifications End States, NEDC-32988-ADresden
Quad Cities
Clinton
30 January 2009Clinton, Unit 1, Dresden, Units 2 & 3 and Quad Cities Units 1 & 2 - Additional Information Supporting Requests for License Amendments to Adopt TSTF-423, Technical Specifications End States, NEDC-32988-A
RS-08-161, Byron, Units 1 and 2 - Technical Specification BasesByron15 December 2008Byron, Units 1 and 2 - Technical Specification Bases
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification BasesBraidwood15 December 2008Braidwood, Units 1 and 2 - Technical Specification Bases
RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5LaSalle23 October 2008LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5
RS-08-132, Calculation L-003068, Re-analysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms, Revision 1, Attachment 7LaSalle10 October 2008Calculation L-003068, Re-analysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms, Revision 1, Attachment 7
RS-08-050, Exelon Generation and Amergen Energy Co, Llc., Three Month Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.Oyster Creek
Dresden
Quad Cities
Peach Bottom
Three Mile Island
Limerick
LaSalle
Byron
Braidwood
11 April 2008Exelon Generation and Amergen Energy Co, Llc., Three Month Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Table of Contents Through List of Effective PagesLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Table of Contents Through List of Effective Pages
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 9.0 - Auxiliary SystemsLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 9.0 - Auxiliary Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 8.0 - Electric PowerLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 8.0 - Electric Power
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control SystemsLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 6.0 - Engineered Safety FeaturesLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 6.0 - Engineered Safety Features
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 5.0 - Reactor Coolant System and Connected SystemsLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 5.0 - Reactor Coolant System and Connected Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 3.0 - Design of Structures, Components, Equipment, and SystemsLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 3.0 - Design of Structures, Components, Equipment, and Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 15.0 - Accident AnalysesLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 15.0 - Accident Analyses
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 12.0 - Radiation ProtectionLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 12.0 - Radiation Protection
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 11.0 - Radioactive Waste ManagementLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 11.0 - Radioactive Waste Management
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 1.0 - Introduction and General Description of PlantLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 1.0 - Introduction and General Description of Plant
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix NLaSalle14 April 2008LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Technical Specification BasesLaSalle14 April 2008LaSalle, Units 1 and 2, Technical Specification Bases
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements ManualLaSalle14 April 2008LaSalle, Units 1 and 2, Technical Requirements Manual
RS-08-025, LaSalle, Units 1 and 2, Response to Request for Additional Information Related to Relief Request I3R-11, Hydrogen Recombiner System Piping - 10 CFR 50.55a(a)(3)(i).LaSalle6 March 2008LaSalle, Units 1 and 2, Response to Request for Additional Information Related to Relief Request I3R-11, Hydrogen Recombiner System Piping - 10 CFR 50.55a(a)(3)(i).
RS-07-143, LaSalle, Unit 1, Withdrawal of Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.LaSalle12 October 2007LaSalle, Unit 1, Withdrawal of Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.
RS-07-139, Braidwood, Units 1 and 2, Byron, Units 1 and 2, Response to Request for Additional Information Regarding Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.Byron
Braidwood
10 October 2007Braidwood, Units 1 and 2, Byron, Units 1 and 2, Response to Request for Additional Information Regarding Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.
RS-07-124, LaSalle, Unit 1, Additional Information Supporting Request for a License Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.LaSalle7 September 2007LaSalle, Unit 1, Additional Information Supporting Request for a License Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.
RS-07-118, Dresden, Units 2 and 3, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement ProcessDresden9 October 2007Dresden, Units 2 and 3, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
RS-07-117, Quad Cities, Units 1 and 2, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement ProcessQuad Cities9 October 2007Quad Cities, Units 1 and 2, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
RS-07-113, LaSalle, Units 1 and 2, Additional Information Supporting Request for Emergency License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink.LaSalle2 August 2007LaSalle, Units 1 and 2, Additional Information Supporting Request for Emergency License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink.
RS-07-075, Clinton, Unit 1, Withdrawal of Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program.Clinton30 April 2007Clinton, Unit 1, Withdrawal of Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program.
RS-07-074, Clinton Power Station, Unit 1, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement ProcessClinton21 June 2007Clinton Power Station, Unit 1, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
RS-07-051, LaSalle, Unit 1, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.LaSalle18 June 2007LaSalle, Unit 1, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.
RS-07-044, Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing ProgramOyster Creek
Dresden
Quad Cities
Peach Bottom
Three Mile Island
Limerick
Byron
Braidwood
8 August 2007Exelon Generation Company, LLC, and Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program
RS-07-034, LaSalle County Station, Units 1 and 2, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection (TAC Nos. MD0540 and MD0541LaSalle6 April 2007LaSalle County Station, Units 1 and 2, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection (TAC Nos. MD0540 and MD0541)
RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement ProcessOyster Creek
Dresden
Quad Cities
Peach Bottom
Three Mile Island
Limerick
LaSalle
Byron
Braidwood
Clinton
12 April 2007Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
RS-06-176, Braidwood Units 1 & 2, Byron Units 1 & 2, LaSalle Units 1 & 2, Site-Specific Decommissioning Cost EstimatesLaSalle
Byron
Braidwood
18 December 2006Braidwood Units 1 & 2, Byron Units 1 & 2, LaSalle Units 1 & 2, Site-Specific Decommissioning Cost Estimates
RS-06-154, LaSalle County Station, Units 1 & 2, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program.LaSalle17 November 2006LaSalle County Station, Units 1 & 2, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program.
RS-06-151, Clinton Power Station, Unit 1, Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program.Clinton16 November 2006Clinton Power Station, Unit 1, Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program.
RS-06-149, LaSalle County Station, Units 1 & 2, Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical PowerLaSalle12 October 2006LaSalle County Station, Units 1 & 2, Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power
RS-06-141, LaSalle, Units 1 and 2 - Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement ProcessLaSalle18 October 2006LaSalle, Units 1 and 2 - Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
RS-06-126, LaSalle Units 1 & 2, Additional Information Supporting License Amendment Request Associated with Direct Current Electrical PowerLaSalle13 September 2006LaSalle Units 1 & 2, Additional Information Supporting License Amendment Request Associated with Direct Current Electrical Power
RS-06-048, Lasalle ILRT Interval Extension Risk AssessmentLaSalle31 March 2006Lasalle ILRT Interval Extension Risk Assessment
RS-06-026, Calculation QDC-0000-N-1266, Revision 2, Re-Analysis of Main Steam Line Break Accident Using Alternative Source Terms.Quad Cities31 January 2006Calculation QDC-0000-N-1266, Revision 2, Re-Analysis of Main Steam Line Break Accident Using Alternative Source Terms.
RS-06-019, Response to NRC Request for Additional Information with Respect to Request for License Amendment Related to Application of Alternative Radiological Source TermByron
Braidwood
13 February 2006Response to NRC Request for Additional Information with Respect to Request for License Amendment Related to Application of Alternative Radiological Source Term
RS-06-004, Additional Information Supporting Request for License Amendment Regarding Offsite Power Instrumentation and Voltage ControlDresden13 January 2006Additional Information Supporting Request for License Amendment Regarding Offsite Power Instrumentation and Voltage Control
RS-06-003, LaSalle, Units 1 and 2, Request for a License Amendment to Revise Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak DetectionLaSalle16 March 2006LaSalle, Units 1 and 2, Request for a License Amendment to Revise Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection
RS-05-037, Dresden, Units 2 and 3, Request for License Amendment Regarding Offsite Power Instrumentation and Voltage ControlDresden4 April 2005Dresden, Units 2 and 3, Request for License Amendment Regarding Offsite Power Instrumentation and Voltage Control
RS-05-005, Exelon Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability ReviewsDresden
Quad Cities
5 January 2005Exelon Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews
RNP-RA/17-0037, H.B. Robinson, Unit 2, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup TRobinson27 September 2017H.B. Robinson, Unit 2, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transfo
RNP-RA/16-0057, License Amendment Request to Modify the Licensing Basis Alternate Source TermRobinson14 September 2016License Amendment Request to Modify the Licensing Basis Alternate Source Term
RNP-RA/16-0046, H.B. Robinson, Unit 2 and ISFSIs - Transmittal of Emergency Plan, Emergency Implementing Procedure Revisions, and 10 CFR 50.54(q) Summary of AnalysesRobinson
07200003
07200060
30 June 2016H.B. Robinson, Unit 2 and ISFSIs - Transmittal of Emergency Plan, Emergency Implementing Procedure Revisions, and 10 CFR 50.54(q) Summary of Analyses
RNP-RA/15-0101, H.B. Robinson, Unit 2 - Response to NRC Request for Additional Information Regarding License Amendment Request to Change Emergency Action Levels (Eals) Scheme Based on NEI 99-01, Revision 6Robinson19 November 2015H.B. Robinson, Unit 2 - Response to NRC Request for Additional Information Regarding License Amendment Request to Change Emergency Action Levels (Eals) Scheme Based on NEI 99-01, Revision 6
RNP-RA/15-0090, H.B. Robinson, Unit 2 - Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate TRobinson19 November 2015H.B. Robinson, Unit 2 - Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test In
RNP-RA/15-0034, H.B. Robinson, Unit 2 - Proposed Changes to Emergency PlanRobinson13 May 2015H.B. Robinson, Unit 2 - Proposed Changes to Emergency Plan
RNP-RA/15-0021, H.B. Robinson, Unit 2, Supplemental Response to 120-Day Response Submittal to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection (NFPA) Standard 805Robinson1 April 2015H.B. Robinson, Unit 2, Supplemental Response to 120-Day Response Submittal to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection (NFPA) Standard 805
RNP-RA/13-0117, H.B. Robinson Unit 2, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) InstrumentationRobinson10 February 2014H.B. Robinson Unit 2, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation
RNP-RA/12-0137, H. B. Robinson, Unit 2, and Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Revision and 10 CFR 50.54(q) Summary of AnalysisRobinson
07200003
07200060
31 December 2012H. B. Robinson, Unit 2, and Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Revision and 10 CFR 50.54(q) Summary of Analysis
RNP-RA/08-0026, H. B. Robinson, Unit 2, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water ReactorsRobinson7 March 2008H. B. Robinson, Unit 2, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
RIS 2012-11, NRC Staff Position on Applying Boiling Water Reactor Technical Specification Requirements During Operations with a Potential for Draining the Reactor Vessel26 September 2012NRC Staff Position on Applying Boiling Water Reactor Technical Specification Requirements During Operations with a Potential for Draining the Reactor Vessel
RIS 2012-11, NRC Staff Position on Applying Boiling Water Reactor Technical Specification Requirements During Operations With a Potential For Draining the Reactor Vessel26 September 2012NRC Staff Position on Applying Boiling Water Reactor Technical Specification Requirements During Operations With a Potential For Draining the Reactor Vessel
RIS 2008-27, Staff Position on Extension of the Containment Type a Test Interval Beyond 15 Years Under Option B of Appendix J to 10 CFR Part 508 December 2008Staff Position on Extension of the Containment Type a Test Interval Beyond 15 Years Under Option B of Appendix J to 10 CFR Part 50
RIS 2008-12, Enclosure 1: Information That NRC Staff May Require To Authorize Extended Interim Storage of Low-Level Radioactive Waste9 May 2008Enclosure 1: Information That NRC Staff May Require To Authorize Extended Interim Storage of Low-Level Radioactive Waste
Enclosure 3 - Bibliography
Enclosure 2: List of Low-Level Radioactive Waste Compacts and Unaffiliated States
Enclosure 4: List of Recently Issued FSME Generic Communications
RIS 2006-10, NRC Regulatory Issue Summary NRC Regulatory Issue Summary 2006-010 - Regulatory Expectations with Appendix R Paragraph Iii.G.2 Operator Manual Actions30 June 2006NRC Regulatory Issue Summary NRC Regulatory Issue Summary 2006-010 - Regulatory Expectations with Appendix R Paragraph Iii.G.2 Operator Manual Actions
RIS 2006-10, NRC Regulatory Issue Summary NRC Regulatory Issue Summary 2006-010 - Regulatory Expectations with Appendix R Paragraph III.G.2 Operator Manual Actions30 June 2006NRC Regulatory Issue Summary NRC Regulatory Issue Summary 2006-010 - Regulatory Expectations with Appendix R Paragraph III.G.2 Operator Manual Actions
RC-93-0310, Virgil C. Summer Nuclear Station (VCSNS) - Technical Specification Change - TSP 930011 Accident Monitoring InstrumentSummer17 December 1993Virgil C. Summer Nuclear Station (VCSNS) - Technical Specification Change - TSP 930011 Accident Monitoring Instrument
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and SystemsSummer31 May 2018Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and SystemsSummer25 May 2016Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EASummer7 April 2014Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EAL
RC-13-0140, Virgil C. Summer, Unit 1 - 10 CFR 71.95 Report on the 8-120B CaskSummer
07109168
20 September 2013Virgil C. Summer, Unit 1 - 10 CFR 71.95 Report on the 8-120B Cask
RC-13-0037, Virgil C. Summer Nuclear Station, Unit 1, License Amendment Request - LAR (13-00705) Technical Specification Change to Extend Integrated Leak Rate Test Frequency to 15 YearsSummer3 April 2013Virgil C. Summer Nuclear Station, Unit 1, License Amendment Request - LAR (13-00705) Technical Specification Change to Extend Integrated Leak Rate Test Frequency to 15 Years
RC-12-0141, Virgil C. Summer, Unit 1, Response to Request for Additional Information License Amendment Request LAR 10-03912 Technical Specification Change Request for TS 3.5.4, Refueling Water Storage Tank (RWST)Summer20 September 2012Virgil C. Summer, Unit 1, Response to Request for Additional Information License Amendment Request LAR 10-03912 Technical Specification Change Request for TS 3.5.4, Refueling Water Storage Tank (RWST)
RC-11-0158, Virgil C. Summer, Unit 1 - License Amendment Request - LAR (11-04569), Technical Specification Change to Extend Integrated Leak Rate Test Interval One-TimeSummer12 October 2011Virgil C. Summer, Unit 1 - License Amendment Request - LAR (11-04569), Technical Specification Change to Extend Integrated Leak Rate Test Interval One-Time
RC-11-0157, Virgil C. Summer, Unit 1 - License Amendment Request LAR 11-04821, Request for Prior NRC Approval to Exempt Five-High-Head Safety Injection Containment Isolation Valves from Local Leak Rate Testing RequirementsSummer12 October 2011Virgil C. Summer, Unit 1 - License Amendment Request LAR 11-04821, Request for Prior NRC Approval to Exempt Five-High-Head Safety Injection Containment Isolation Valves from Local Leak Rate Testing Requirements
RC-11-0094, Virgil C. Summer, Unit 1 - Technical Specification Bases Revision Updated Through June 2011Summer31 August 2011Virgil C. Summer, Unit 1 - Technical Specification Bases Revision Updated Through June 2011
RC-11-0052, Virgil C. Summer, Unit 1, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.Summer2 May 2011Virgil C. Summer, Unit 1, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.
RC-09-0004, Virgil C. Summer - License Amendment Request - LAR 04-02911 License Amendment and Related Technical Specification Changes to Implement Full-scope Alternative Source Term in Accordance with 10 CFR 50.67Summer17 February 2009Virgil C. Summer - License Amendment Request - LAR 04-02911 License Amendment and Related Technical Specification Changes to Implement Full-scope Alternative Source Term in Accordance with 10 CFR 50.67
RC-07-0025, Virgil C. Summer, License Amendment Request - LAR 05-3594 Steam Generator Tube IntegritySummer15 February 2007Virgil C. Summer, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity
RC-06-0084, Virgil C. Summer, License Amendment Request - LAR 05-3594, Steam Generator Tube IntegritySummer24 May 2006Virgil C. Summer, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity
RA18-084, LaSalle County Station, Unit 2 - Post Accident Monitoring ReportLaSalle17 October 2018LaSalle County Station, Unit 2 - Post Accident Monitoring Report
RA18-059, LaSalle, Units 1 and 2 - Inservice Testing Program Plan, Technical Position TP-05LaSalle18 July 2018LaSalle, Units 1 and 2 - Inservice Testing Program Plan, Technical Position TP-05
RA18-018, LaSalle, Units 1 & 2 - Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, TornadoLaSalle20 March 2018LaSalle, Units 1 & 2 - Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado
RA17-086, LaSalle County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01LaSalle10 November 2017LaSalle County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01
RA17-086, LaSalle - Submittal of Program Plan Associated with the Fourth Lnservice Inspection (ISI) Interval and the Third Containment Lnservice Inspection (Cisi) IntervalLaSalle10 November 2017LaSalle - Submittal of Program Plan Associated with the Fourth Lnservice Inspection (ISI) Interval and the Third Containment Lnservice Inspection (Cisi) Interval
RA17-072, LaSalle, Unit 1 - Post Accident Monitoring ReportLaSalle2 August 2017LaSalle, Unit 1 - Post Accident Monitoring Report
RA17-069, LaSalle, Unit 2 - Post Accident Monitoring ReportLaSalle21 July 2017LaSalle, Unit 2 - Post Accident Monitoring Report
RA17-055, LaSalle County Station, Unit 2 - Post-Outage 90-Day Lnservice Inspection (ISI) Summary ReportLaSalle7 June 2017LaSalle County Station, Unit 2 - Post-Outage 90-Day Lnservice Inspection (ISI) Summary Report
RA17-031, LaSalle County Station, Unit 1 - Post Accident Monitoring ReportLaSalle31 March 2017LaSalle County Station, Unit 1 - Post Accident Monitoring Report
RA15-032, LaSalle, Units 1 and 2 - Response to NRC Request for Additional Information on Severe Accident Mitigation Alternatives Review, Dated April 30, 2015 Regarding the License Renewal Application Environmental ReviewLaSalle29 May 2015LaSalle, Units 1 and 2 - Response to NRC Request for Additional Information on Severe Accident Mitigation Alternatives Review, Dated April 30, 2015 Regarding the License Renewal Application Environmental Review
RA15-028, LaSalle, Unit 2 - Post-Outage 90-Day Inservice Inspection (ISI) Summary ReportLaSalle26 June 2015LaSalle, Unit 2 - Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RA14-059, LaSalle, Units 1 and 2 - Applicant'S Environmental Report, Operating License Renewal Stage, Appendix C - EndLaSalle9 December 2014LaSalle, Units 1 and 2 - Applicant'S Environmental Report, Operating License Renewal Stage, Appendix C - End
RA14-018, LaSalle County Station Unit 1, Post-Outage 90-Day Inservice (ISI) Summary ReportLaSalle29 May 2014LaSalle County Station Unit 1, Post-Outage 90-Day Inservice (ISI) Summary Report
RA13-023, LaSalle, Unit 2, Post-Outage 90-Day Inservice Inspection (ISI) Summary ReportLaSalle31 May 2013LaSalle, Unit 2, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RA13-020, LaSalle County Station, Units 1 and 2, Submittal of 2012 Annual Radioactive Effluent Release ReportLaSalle26 April 2013LaSalle County Station, Units 1 and 2, Submittal of 2012 Annual Radioactive Effluent Release Report
RA12-018, LaSalle County Station, Unit 1, Post-Outage 90-Day Inservice Inspection (ISI) Summary ReportLaSalle5 June 2012LaSalle County Station, Unit 1, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RA11-024, LaSalle, Unit 2 - Post-Outage 90-Day Inservice Inspection (ISI) Summary ReportLaSalle3 June 2011LaSalle, Unit 2 - Post-Outage 90-Day Inservice Inspection (ISI) Summary Report
RA10-037, LaSalle, Units 1 & 2, Submittal of 2009 Regulatory Commitment Change Summary ReportLaSalle7 May 2010LaSalle, Units 1 & 2, Submittal of 2009 Regulatory Commitment Change Summary Report
... further results