Letter Sequence Supplement |
---|
EPID:L-2019-LLA-0134, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls (Approved, Closed) |
|
|
|
---|
Category:Letter type:RS
MONTHYEARRS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-21-009, Proposed Relief Request Associated with Code Case N-9212022-01-18018 January 2022 Proposed Relief Request Associated with Code Case N-921 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-114, Request for Exemption from 10 CFR 2.109(b)2021-10-28028 October 2021 Request for Exemption from 10 CFR 2.109(b) RS-21-110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-19019 October 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-103, Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station2021-09-28028 September 2021 Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station RS-21-097, Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning2021-09-15015 September 2021 Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes 2023-08-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments ML21181A0572021-11-0404 November 2021 Issuance of Amendment No. 344 Adoption of TSTF-545 JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML21144A1072021-05-17017 May 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-021, License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition2021-03-17017 March 2021 License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-21-016, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2021-01-29029 January 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems JAFP-20-0083, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule2020-12-11011 December 2020 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-20-0080, Application to Revise Surveillance Requirement (SR) 3.5.1.62020-12-11011 December 2020 Application to Revise Surveillance Requirement (SR) 3.5.1.6 ML20323A2542020-11-18018 November 2020 Markup of Proposed Technical Specifications Bases Pages RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-132, License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2020-10-29029 October 2020 License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-20-116, License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Unit 1 Technical Specifications Section 6.1, Responsibility, and Units 2 and 3 Technical Specifications 1.1, Definitions, and 5.0, Administrative JAFP-20-0047, License Amendment Request: Application to Modify Technical Specifications 3.6.1.3, Primary Containment Isolation Valves2020-06-30030 June 2020 License Amendment Request: Application to Modify Technical Specifications 3.6.1.3, Primary Containment Isolation Valves JAFP-20-0046, License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item.2020-06-30030 June 2020 License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item. RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process RS-20-025, Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2020-02-24024 February 2020 Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls JAFP-20-0012, License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line...2020-01-23023 January 2020 License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line... ML19295G7832019-12-19019 December 2019 Issuance of Amendment No. 331 Regarding Change to Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters RS-19-093, Secondary Containment Drawdown Analysis2019-10-17017 October 2019 Secondary Containment Drawdown Analysis ML19277D5522019-10-0404 October 2019 Draft James A. FitzPatrick Nuclear Power Plant - Emergency License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19277G0852019-10-0404 October 2019 Emergency License Amendment Request: One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19276G3132019-10-0202 October 2019 Draft Exigent License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source JAFP-19-0092, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2019-09-26026 September 2019 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers JAFP-19-0089, License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads2019-09-12012 September 2019 License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2019-09-0505 September 2019 License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) ML19157A2032019-07-11011 July 2019 Issuance of Amendment No. 325 Reactivity Anomalies Surveillance JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program 2023-08-31
[Table view] |
Text
200 Exelon Way Exelon Generation Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 RS-20-025 February 24, 2020 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 James A FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333
Subject:
Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls
Reference:
- 1. Exelon Letter RS-19-039 to U. S Nuclear Regulatory Commission, "Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls," dated June 26, 2019 (ADAMS Accession No. ML19178A304)
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), proposed a change to the Technical Specifications (TS), Appendix A of Renewed Facility Operating Licenses for Braidwood, Byron, Calvert Cliffs, Dresden, James A FitzPatrick, LaSalle County, Limerick, Nine Mile Point, Peach Bottom Atomic Power, Quad Cities, R.E. Ginna and Three Mile Island nuclear stations, and Facility Operating License for Clinton Power Station, to request common language for the Technical Specification High Radiation Area Administrative Controls (Reference 1).
Recently, during preparation and review of clean TS pages to be submitted to NRC, it was discovered that the TS marked-up pages for Dresden and James A FitzPatrick nuclear stations had been inadvertently omitted from Reference 1. The oversight had occurred during the final assembly of the License Amendment Request (LAR) package before electronically submitting to the NRC.
The marked-up TS pages for Dresden and James A FitzPatrick nuclear stations are included in Attachment 1.
U.S. Nuclear Regulatory Commission Exelon Fleet LAR-Common Language for TS HRA Administrative Controls February 24, 2020 Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Attachment 1 of the Reference 1 letter. EGC has concluded that the information provided in this response does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition, EGC has concluded that the information in this supplemental letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
The proposed changes had been previously reviewed by each station's Plant Operations Review Committee in accordance with the requirements of the EGC Quality Assurance Program.
This amendment request contains no regulatory commitments .
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), EGC is notifying the states of Illinois and New York of this request for changes to the Technical Specifications by transmitting a copy of this letter and its attachment to the designated State officials.
If you have any questions or require additional information, please contact Mr. Frank J. Mascitelli at (610) 765-5512.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 241h day of February 2020.
Respectfully, David P. Helker Sr. Manager, Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
- 1. Proposed Technical Specifications Markup Pages (Dresden and FitzPatrick Stations) cc: Regional Administrator - NRC Region I Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - James A. FitzPatrick Nuclear Power Plant NRC Project Manager, NRR - Dresden Nuclear Power Station NRC Project Manager, NRR - James A. FitzPatrick Nuclear Power Plant Illinois Emergency Management Agency - Division of Nuclear Safety A. 1,.. Peterson, NYSERDA
Attachment 1 Proposed Technical Specifications Markup Pages (Dresden and FitzPatrick Stations)
Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls Dresden, Units 2 & 3 TS Pages 5.7-1, 2 James A. FitzPatrick TS Pages 5.7-1, 2, 3, 4
High Radiation Area 5.7 5.0 ADMINISTRATIVE coz lnsert 1 I 5.7 High Radiation Area 12 PursuaAt to 10 CFR 20 , paragraph 20.160l(e) , iA lieu of the requiref!leAts of 10 CFR 20 . 1601 , eaeh high raeliatioA area , as elefiAeel iA 10 CFR 20 , iA whieh the iAteAsity of radiatioA is
~ fflref!l/hr at 30 effl (12 iA . ) , shall ee earricaelee aAEl coAspieuously postce as a high raeliatioA area aAEl cAtraAee thereto shall be eoAtrellee ey requiriAg issuaAee ef a RaeiatieA Werk Perfflit (RWP) (er equivaleAt eecumeAt) . IAeivieluals qualifieel iA raeiatieA pretectioA preceeures (e . g., radiatieA preteetioA techAieiaAs) er perseAACl escorted by such iAeivieluals ffiay ee exefflpt freffi the RWP issuaAce requiremeAt euriAg the perfermaAee ef their assigAee duties , previeee tl=ley are etl=lerwise fellewiAg plaAt radiatioA preteetieA proceeures fer eAtry iAto high raeliatieA areas .
AAy iAdivielual er group af iAdividuals perffiittee te eAter such areas shall ee provieled with or accompaAiee by oAe er more of the follo*..*iAg:
- r. A raciiatieA fflaAitari19g eevice that eaAtiAuously iAelicates the raeliatioA elose rate iA the area .
-Ir:- A raeiatiOA ffiOAitoriAg ee*,*ice tl=lat 9AtiAUOl:lS1)' iAtegrates the raciiatioA eese rate iA the area aAel alarffis wheA a preset iAtegratee dose is receives . EAtry iAta such areas witl=I tl=lis fflOAitoriAg device may ee fflaele after the elose rate levels iA tl=le area !=lave eeeA estaelisl=leel aAel persoAAel are a1;a re of tl=leffl .
~ AA iAelivielual qualifies iA raeliatieA protectioA preeeelures with a raeliatioA ease rate moAitoriAg elevice , who is respoAsiele for provieliAg positive coAtrol over the activities withiA the area a19el shall perform perieelie raeli ati 019 SUF't'ei 11 a Ace at the freQUeAEY speci fi eel i A the RIJP (or equivaleAt elocumeAt) .
IA adeitioA te the requiremeAts of SpecificatioA 5. 7. 1 , areas accessisle to persoAAel with raeliatioA levels) 1000 mrem/hr at 30 cm (12 iA . ) from the radiatioA so~rce or froffl aAy s~rface which the radiatioA peAetrates shall require the followiA§:
ih- 9oors shall se l ocl<eel to preveAt uAa~thori zeel eAtry aAEI shall fist [:)PeveAt iAelivie!uals fPOffi leaviAg Hie at'ea . f.A.
place of lockiA§ the eloor , elirect or electt'oAic sur~eillaRce (EOAtiAUES)
Dresden 2 and 3 5. 7 -1 Amendment No. 185/180
High Radiation Area 5.7 : 111gA RasiatieA APea
~ (ceAtiAues) that is capable ef pPeveAtiAg unautherizes entry ffiay be
~ The l<eys sAal l Be ff!ai Atai nee unser tAe aeffii ni stPati ve coAtrol ef tAe sRift ffianager eA euty er raeiatioA pPoteetion supePvisieA .
- - PePseAnel aceess and e>(pesuFe ceAtrel requi reffients ef activities beiRg perferffied withiA tAese areas sAall be specified By aR approves RWP (er equivaleRt eocumeAt) .
-=- Each pePSBR eAteri A§ tAe aioea SAal 1 BC pre¥i Eled 'iii tA aA alarffiiAg raEliatieA meAiteriRg sevice tAat centiAueusly iAtegrates tAe radiatien sese rate (sucA as aA eleetroAic dosiffieter) . SurveillaRce aAs raeiatioR ffiOAitoriAg 13y a rasiatioA protectieA tecAniciaA ff!ay be substitutes for aR alarming sosiff!eter .
For iAsividual AigA rasiatieR areas witA radiatieA levels of
> 1000 ff!PCffi/Ar at 30 Cffi (12 iA . ) , accessible te perseAAel , that are located within large areas whePe ne eAclesure exists fer purpeses ef lacking , aAe whePe Re eRelesure can be reaseRably ceAstrueted areuRd tRe iAsivisual area , that iAdivieual area sRall be barricadee ans ceAspicueusly pasted , aAEl a flasAiAg ligRt shall Be activates as a warniAg device .
Dresden 2 and 3 5.7-2 Amendment No. 185/180
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS
- 5. 7 High Radiation Ar/ j lnsert 1 I
- ~af\~!d::P:~e~ 8~=g~~:~ ~:d!:~!!~)a~a! 9 i~~1:::te~ th:":a=:~!~i~:;=~~:~e~;
9 paragraph 20.169l(a) and Cb) ef 19 CFR Part 29:
~~i~~~t~f::i1::1'~::U~ ~'1:1.tn~.~tt~~et1r at a-; Each entrance er aeeess l'f}int te sueh an area shall be
- !:::~~~i=~~~~~~~e~~~;~~~;::~e~
as necessary te permit entry er exit ef persennel er eqtJipmertt.
Ir. Aeeess te. and aetiYities in. each sueh area shall be eentrelled by means ef a Radiatien Werk Permit (RWP) er
~::::a~=":";"~:n!d~!;:e!a~ee:~::::t :~d :th:~ ::~~~~~!~e 1 6 1 radiatien preteetien eqtJipment and 111eastJres.
e-: Indi~iduals qualified in radiation preteetien preeedtJres and perso"nel eentintJeusly escorted by stJeh ;ndi~idtJals may be eMempted frem the re(ftlirement fer an RWP or e~tJivalent while performing their assigned duties provided they are following plant radiatien preteet;en preeedures for entry ta. exit fram, and werk in sueh areas.
&: Eaeh ifldiviaual er grettp enteriflg sueh an area shall pessess:
b A rae:ii ati efl merti ter*h~g Ele*ii ee tt'lat eenti rtttotts l y displays radiatiefl dese rates in tt'le area. er 2-; A radiatien meHitering deviee that eerttinuously irttegrates the radiatien dese rates in the area and alarms wheA the deviee's dese alarm setpoiftt is reaehed, with a pre set alarm setpeint. er 3-:: A radiatiefl meniteriflg deviee that eontinttottsly traflsmits dose rate artd cum~lative dose information to a remete receiver menitered by radiatien preteetion persenrtel responsible fer eantrelling persoflnel radiation exposttre within the area, or JAFNPP 5.7-1 Amendment 2-14
High Radiation Area 5.7 5.7 High Radiation Area
- 4. A self read;ng desimeter (e.g., peeket ieAizatieA ehHmber er eleetrenie desiffieter) aAd, (8) Be Hnder the sur¥eillaAee, as s~eeified iA the RWP er eqt:tivalent. while in the area. ef an individual qualified iA radiatien preteetieA preeedHPes.
equipped with a radiatieA meniteriAg de¥iee that eeAtiAHeHsly displays radiatien Elese rates in the area. whe is respensiele fer eeRtrelliRg persennel expest:tre withiA the area, er (b) Be uAder the sur~eillanee. as speeified in the RWP er eqt:tivaleAt, while iA the area. by means ef elesed eireuit televisien. ef perseRRel ~ualified i~rr::~:~!~~i~;e~~!!~~efr~::::;~:R =:::::~:a~~
the area. and with the means te eeRIRt:IAieate with iAdividHHls iA the area whe are eevered by sueh st:tr*1e; 11 aAee.
e: Exeept f6r iAdividttals qt:talified iA radiatieA preteetieA preeedures, er perseAnel eentint:teusly eseerted by sueh individuals, entry inte such areas shall be made enly a~er dese rates iH the area have heen determined and entry perseflnel are kAewleegeaele ef tRem. TRese eeAtiAueusly eseerted persenHel will recei¥e a pre jeb briefiAg ~Pier te entry iAte sueh areas. This eese rate determ1Aatien.
knewledge, affd pre jab Bfi@fiAg dees A6t re~t:tire deeumentatieA prier te initial entry.
a-: Eaeh em:raAee er aecess peiAt ta st:teh aA area shall be eenspieuet:tsly pest-ea as a high radiatiefl area aAd shall be Ceentiftt:Jed)
JAFNPP 5.7-2 Amendment ~
High Radiation Area 5.7 5.7 High Radiation Area pre~ided with a leeked deer er gate that preveAts unauthorized entry, er be eentinueusly guarded to pre~ent unauthorized persennel entr:Y. and, in addition:
!-; All sueh deer and gate keys shall be mai"tained under the adtftinistrative eentrel ef the shift maAeger, radiatien pretectien manager, er designee.
2-: Beers and gates shall remain loeked exeept during periods of persennel er equipment entry or ex;t.
tt: Aeeess ta, and aetivities in, eaeh sueh area shall be eentrelled by means ef an RWP er equi~alent that ineludes speeificatien ef radiation dose rates in the iRll'lediate work area(s) and ether apprepriate radiatien preteetion equipnent and measures.
e-: lndi~iduals qualified in radiatien pretectien proeedures may ee e~empted frem the requirement f-er an RWP or equivalent while perferming radiatien surveys in sueh areas provided they are f-ellewing plant radiatien preteetion procedures for entry te, exit frem, and werk in sueh areas.
Et-: Each indi~idual er group entering such an erea shall possess.
~ A radiatieA 11e"itering device that eontinHou!ly integrates the radiation dose r8tes in the erea end alarms when the deviee's dose alarm setpoint is reaehed, with a pre set alarm setpoint. or 2-; A radiatien monitering deviee that eontinHOH!ly tPaAs111i ts dese Pate and e1:1111ul ath'e dose i nfermati on to a rellete reeeiver monitored by radiatioft protection
~:~::;~:! :;:~::::b~t::~ ;~~t:~!! ~~;=:"~!n3 te 1
CEMlllllHAieate with aAd cefftrel every individual in the area, er (eentiftued)
JAFNPP 5.7-3 Amendment r14
High Radiation Area 5.7 5.7 High Radiation Area
- 3. A self readiHg dosimeter (e.g., pee~et ieHilatien chember er eleetrenie desimeter) and.
<e> Be Hnder the surveillaHee, as specified in the RWP or equivalent, while in the area , ef an indi¥idual qualified in radiatien preteetien preeedures.
equipped w;th a radiatien 1116nitering de¥iee that continuously displays radiation dese rates in the erea: whe is respensi ble fer eentralling persennel expesure within the area. er (b) Be under the surveillaHee. as specified in the RWP or equi¥aleHt, while iH the area, by means ef elesed circuit televisien, ef persennel qualified
- rr::~:;:~~i~;e::~:!~e~r~==~:;::n ==:~:~!e~=
the area. aHd with the 111eans te eeHIRunicate with end eentrel every individual in the area. er.
4: In those eases where eptiens 2 end 3. abeve . are imprectieal or determined to be inconsistent with the "A l:: As
- bt " * * -le, r~ia~en lft:~1t!~:~~ de~ie: ;=:: e:nt~~===~~~di:plays rediat;en dose rates in the area may be used.
e: Except fer individuals qualified in radiation preteetieH procedures . er persenHel eentiHueusly escorted by such indhiduals, efltry inte sueh areas shall be made enly after dese rates iH the area ha~e been determined and entPy persennel are knewledgeaele ef them. These eentiAueHsly eseerted perseflnel will reeei~e a pre jee briefing prier te entry inte sueh areas. This dese rate determinatie",
kHewledge, and pre jeb briefing does net require deettme"tatien prier te entPy.
f: SHeh indi¥idua1 areas that are within a larger area where ne
=~:~:::~ ::~s;:a::~a= g:r~=;t~:ei:~!~~H~~d~ere ne individual area need net be eentrelled by a locked door or gate. nor eenspieueusly guarded, but shall be barricsded,
- =~vv1~
- e:~irv~:;:e:f :~= :r~!e::1~ ::~~~: :!:~~:~g 11ght JAFNPP 5.7-4 Amendment m
Insert 1 Pursuant to 10 CFR Part 20, paragraph 20.1601 (c), in lieu of the requirements of paragraph 20.1601 (a) and 20.1601 (b) of 10 CFR Part 20:
- 5. 7 .1 Access to each high radiation area, as defined in 10 CFR 20, in which an individual could receive a deep dose equivalent > 0.1 rem in one hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation) shall be controlled as described below to prevent unauthorized entry.
- a. Each area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
- b. Entrance shall be controlled by requiring issuance of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rate in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may, for the performance of their assigned duties in high radiation areas, be exempt from the preceding requirements for issuance of an RWP or equivalent provided they are otherwise following plant radiation protection procedures for entry into, exit from, and work in such high radiation areas.
- d. Each individual or group of individuals permitted to enter such areas shall possess, or be accompanied by, one or more of the following:
- 1. A radiation monitoring device that continuously indicates the radiation dose rate in the area.
- 2. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset setpoint is reached. Entry into high radiation areas with this monitoring device may be made after the dose rate in the area has been determined and personnel have been made knowledgeable of it.
- 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area.
- 4. An individual qualified in radiation protection procedures equipped with a radiation dose rate monitoring device. This individual shall
be responsible for providing positive radiation protection control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by radiation protection supervision.
5.7.2 In addition to the requirements of Specification 5.7.1, high radiation areas in which an individual could receive a deep dose equivalent > 1.0 rem in one hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation), but less than 500 rads/hour (at 1 meter from the radiation source or from any surface penetrated by the radiation) shall be provided with a locked or continuously guarded door, or gate, or equivalent to prevent unauthorized entry.
- a. The keys to such locked doors or gates, or equivalent, shall be administratively controlled in accordance with a program approved by the radiation protection manager.
- b. Doors and gates, or equivalent, shall remain locked except during periods of access by personnel under an approved RWP, or equivalent, to ensure individuals are informed of the dose rate in the immediate work areas prior to entry.
- c. Individual high radiation areas in which an individual could receive a deep dose equivalent> 1.0 rem in one hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation),
accessible to personnel, that are located within larger areas where no enclosure exists to enable locking, or that are not continuously guarded, and where no lockable enclosure can be reasonably constructed around the individual area require both of the following access controls:
- 1. Each area shall be barricaded and conspicuously posted.
- 2. A flashing light shall be activated as a warning device.