Exelon Generation and Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed OperatorsML072110212 |
Person / Time |
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Site: |
Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Clinton, Quad Cities, LaSalle |
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Issue date: |
07/19/2007 |
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From: |
Cowan P B AmerGen Energy Co, Exelon Generation Co |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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2130-07-20496, 5928-07-20108, RS-07-078 |
Download: ML072110212 (20) |
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Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-120, 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-23-119, 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-23-118, 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-23-117, 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-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 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-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 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-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program 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-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation 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-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process 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-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. 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-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 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-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink 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 2024-01-03
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process 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-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23090A2162023-03-30030 March 2023 Supplement to License Amendment Request - Proposed Changes to TMI-2 Possession Only License and Technical Specifications RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23058A0642023-02-22022 February 2023 License Amendment Request - Three Mile Island, Unit 2, Historic and Cultural Resources Review RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-23-006, Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023 Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML22332A4492022-11-10010 November 2022 License Amendment Request - Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML22313A0502022-11-0707 November 2022 License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Request for Information Regarding Radiation Protection Program Ventilation Controls 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-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly 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-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. 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-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling ML22138A2852022-05-16016 May 2022 (TMl-2) - License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Questions RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock ML22013A1772022-01-0707 January 2022 License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Supplemental Information ML22010A0682022-01-0505 January 2022 Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0002 MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library ML22010A0672022-01-0505 January 2022 Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0001 Determination of the Safe Fuel Mass Limit for Decommissioning TMl-2 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-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments RS-21-108, Application to Revise Technical Specification 3.1.4, Control Rod Scam Times2021-11-16016 November 2021 Application to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021 Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5 RS-21-065, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12021-10-25025 October 2021 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 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 ML21257A4202021-09-14014 September 2021 Request for Licensing Amendment Regarding Transition to GNF3 Fuel ML21188A0202021-08-11011 August 2021 Issuance of Amendment No. 239 One-Time Extension of Containment Type a Integrated Leakage Rate Test Frequency RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-064, License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter2021-06-30030 June 2021 License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter 2023-09-08
[Table view] Category:Technical Specifications
MONTHYEARML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) 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 ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML23032A3602023-03-22022 March 2023 Issuance of Amendment Nos. 279 and 272 New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications ML22217A0442022-12-0707 December 2022 Issuance of Amendment Nos. 292 and 288 Control Rod Scram Times ML22332A4502022-11-10010 November 2022 Attachment 2 - Markup of Technical Specification Pages RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position 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 ML22111A2142022-03-31031 March 2022 2 to Updated Safety Analysis Report, Chapter 16, Technical Specifications RS-22-048, 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls)2022-03-31031 March 2022 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls) ML22087A3942022-03-28028 March 2022 Supplemental Information Supporting License Amendment Request - Proposed Revision to License Conditions and Permanently Defueled Technical Specifications for Permanent Removal of Irradiated Fuel from the Spent Fuel Pool (ISFSI-Only Technica RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements 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 ML21193A1302021-07-14014 July 2021 Correction to Amendment No. 238 Issued June 28, 2021, Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21158A2282021-07-13013 July 2021 Issuance of Amendments to Renewed Facility Operating Licenses a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21265A5362021-06-30030 June 2021 Attachment 2: LaSalle County Station Units 1 & 2 - Proposed Technical Specifications Markups ML21119A0642021-06-25025 June 2021 License Amendment 299 ML21179A0432021-06-21021 June 2021 4 to Final Safety Analysis Report, Chapter 16, Technical Specifications ML21082A4222021-05-27027 May 2021 Issuance of Amendment Nos. 249 and 235 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21118A0572021-04-13013 April 2021 Submittal of Changes to Technical Specifications Bases ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML20352A3812020-12-18018 December 2020 TMI-2 License Transfer Conforming Amendment ML21008A4052020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20261H9252020-12-0202 December 2020 Issuance of Amendment No. 299 for Unit 1 Permanently Defueled Emergency Plan and Emergency Action Level Scheme Changes RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)2020-10-29029 October 2020 Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.32020-04-0101 April 2020 Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19266A6222019-10-29029 October 2019 Issuance of Amendment Nos. 328 and 331 Revising Technical Specifications 3.81, AC Sources - Operating, for a One-Time Extension of Completion Time ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers ML19182A0062019-08-28028 August 2019 Issuance of Amendment Nos. 327 and 330 Reduce High Pressure Service Water System Design Pressure and Temporarily Extend Completion Times ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements 2023-08-30
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An Exelon Company www.exeloncorp.com Nuclear AmerGen Energy Company, LLC 4300 Winfield Road Exelon Generation Warrenville, IL 60555 4300 Winfield Road Warrenville, IL 60555 10 CFR 50.90 RS-07-078 5928-07-20108 2130-07-20496 July 19, 2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 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 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 1 and NPF-1 8 NRC Docket Nos. 50-373 and 50-374 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-1 6 NRC Docket No. 50-219 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No. DPR-50 NRC Docket No. 50-289 01l July 19, 2007 U. S. Nuclear Regulatory Commission Eligibility Requirements for Licensed Operators Page 2
Subject:
License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators
Reference:
Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S. NRC,"Revision to Technical Specification Change Request-Clarification of Requirements for Licensed Operator Qualification and Training," dated June 19, 2002 In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) and AmerGen Energy Company, LLC (AmerGen) are requesting changes to the Technical Specifications (TS), Appendix A of the facility operating licenses listed above.The proposed changes will change the licensed operator training and qualification education and experience eligibility requirements made in the referenced letter, dated June 19, 2002, to the eligibility requirements specified in this letter, dated July 19, 2007. The proposed eligibility requirements correspond to the eligibility requirements contained in National Academy for Nuclear Training (NANT) Academy Document (ACAD)00-003, Revision 1, "Guidelines for Initial Training and Qualification of Licensed Operators." Attachment 1 to this letter provides the evaluation of the proposed changes and the no significant hazards consideration determination.
Attachment 2 provides the existing TS pages marked-up to show the proposed changes.These proposed changes have been reviewed and approved by each station's Plant Operations Review Committee and Nuclear Safety Review Board.There are no regulatory commitments contained within this letter. EGC and AmerGen request approval of the proposed license amendment by July 19, 2008. Once approved, the amendments shall be implemented within 60 days.The States of Illinois, New Jersey, and Pennsylvania are being notified of this request for changes to the TSs by transmitting a copy of this letter and its attachments to the designated State officials.
Should you have any questions concerning this letter, please contact Frank J. Mascitelli at (610)765-5512.I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1 9 th day of July 2007.Respectfully, Pamela B. Cowan Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC AmerGen Energy Company, LLC July 19, 2007 U. S. Nuclear Regulatory Commission Eligibility Requirements for Licensed Operators Page 3 Attachments:
- 1. Evaluation of Proposed Changes 2. Proposed Technical Specifications (Marked-Up Pages)cc: Regional Administrator
-NRC Region I Regional Administrator
-NRC Region III C. Gratton -NRC Project Manager, NRR -(EGC/AmerGen Fleet)NRC Senior Resident Inspector
-Braidwood Station NRC Senior Resident Inspector
-Byron Station NRC Senior Resident Inspector
-Clinton Power Station NRC Senior Resident Inspector
-Dresden Nuclear Power Station NRC Senior Resident Inspector
-LaSalle County Station NRC Senior Resident Inspector
-Oyster Creek Nuclear Generating Station NRC Senior Resident Inspector
-Peach Bottom Atomic Power Station NRC Senior Resident Inspector
-Quad Cities Nuclear Power Station NRC Senior Resident Inspector
-Three Mile Island Nuclear Station Unit 1 NRC Project Manager, NRR -Braidwood Station NRC Project Manager, NRR -Byron Station NRC Project Manager, NRR -Clinton Power Station NRC Project Manager, NRR -Dresden Nuclear Power Station NRC Project Manager, NRR -LaSalle County Station NRC Project Manager, NRR -Oyster Creek Nuclear Generating Station NRC Project Manager, NRR -Peach Bottom Atomic Power Station NRC Project Manager, NRR -Quad Cities Nuclear Power Station NRC Project Manager, NRR -Three Mile Island Nuclear Station Unit 1 Illinois Emergency Management Agency -Division of Nuclear Safety Director, Bureau of Radiation Protection
-Pennsylvania Department of Environmental Resources Director, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection Chairman, Board of County Commissioners of Dauphin County, PA Chairman, Board of Supervisors of Londonderry Township, PA Mayor of Lacey Township, Forked River, NJ R. I. McLean, State of Maryland R. R. Janati, Commonwealth of Pennsylvania Attachment 1 Evaluation of Proposed Changes Technical Specification Unit Staff Qualification Changes for Braidwood Station, Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station and Three Mile Island Nuclear Station
1.0 DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL
ANALYSIS 5.0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration
5.2 Applicable
Regulatory Requirements/Criteria
6.0 ENVIRONMENTAL
CONSIDERATION
7.0 PRECEDENT
8.0 REFERENCES
Attachment 1 Evaluation of Proposed Changes
1.0 DESCRIPTION
In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) and AmerGen Energy Company, LLC (AmerGen) are requesting that the Technical Specifications (TS), Appendix A of the facility operating licenses for Braidwood Station, Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station, and Three Mile Island Nuclear Station under Facility Operating License Nos. NPF-72 and NPF-77, NPF-37 and NPF-66, NPF-62, DPR-1 9 and DPR-25, NPF-1 1 and NPF-1 8, DPR-1 6, DPR-44 and DPR-56, DPR-29 and DPR-30, DPR-50, respectively, be amended as proposed to permit changes to the Unit Staff Qualification education and experience eligibility requirements for licensed operators.
The proposed education and eligibility requirements for licensed operators are the same requirements contained in the National Academy for Nuclear Training (NANT) Academy Document, ACAD 00-003, Revision 1, dated April 2004 (Ref 1). The proposal will bring EGC and AmerGen sites in alignment with current industry practices and facilitate the development of a pre-initial licensed operator training (ILT) program.This proposed License Amendment Request (LAR) involves revising TS Sections 5.3.1/6.3.1,"Unit Staff Qualifications," for operator license applicants in accordance with current industry standards for education and experience eligibility requirements.
These proposed eligibility requirements are identical to the reactor operator and senior reactor operator eligibility requirements contained in NANT ACAD 00-003, Guidelines for Initial Training and Qualification of Licensed Operators, Revision 1, dated April 2004.This LAR provides a discussion and description of the proposed TS changes, a safety assessment of the proposed TS changes, information supporting a finding of No Significant Hazards Consideration, and information supporting an Environmental Assessment.
2.0 PROPOSED CHANGE
Proposed Typical Change to TS 5.3.1/6.3.1"the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure."
3.0 BACKGROUND
The existing TS requirements for Facility Staff Qualifications and licensed operator personnel training programs are based on NRC endorsed industry standards to ensure that a licensee's staff is appropriately qualified and trained for their respective positions.
These requirements were developed based on the pre-1987 revision of 10 CFR 55 and prior to the 1993 edition of 10 CFR 50.120. Current licensed operator qualifications and the licensed operator retraining and replacement programs must also comply with the requirements of 10 CFR 55 and 10 CFR 50.120.Page 1 Attachment 1 Evaluation of Proposed Changes ACAD 00-003, Revision 1, and NUREG-1 021, Revision 9, allow time spent in training before entering the ILT to qualify as experience, but time spent in an NRC-approved training program leading up to license eligibility should normally not be double-counted as experience.
Our current regulatory requirement, as described in flow charts attached to RS-02-100 letter (Ref 2)referenced in TS 5.3.1/6.3.1, and original submittal letter (Ref 3) do not allow any pre-ILT training to count for on-site experience.
The purpose of this license amendment request is to revise Exelon and AmerGen licensed operator education and experience eligibility regulatory requirements to be consistent with Revision 1 of ACAD 00-003 so that pre-ILT training can count for on-site experience.
4.0 TECHNICAL
ANALYSIS On March 20, 1985, the NRC issued the Commission Policy Statement on training and Qualification of Nuclear Power Plant Personnel, which endorsed the training accreditation program developed by INPO, in association with its National Academy for Nuclear Training (NANT). The NRC has documented approval and acceptance of NANT guidelines in RIS 2001-01, "Eligibility of Operator License Applicants," NUREG-1 021, Revision 9, "Operator Licensing Examination Standards For Power Reactors," and Regulatory Guide (RG) 1.8,"Qualification and Training of Personnel for Nuclear Power Plants." These documents state that a facility licensee's training program would be considered approved by the NRC when it is accredited by the National Nuclear Accrediting Board and that NANT guidelines for education and experience outline acceptable methods for implementing the NRC's regulation in this area.The TS Facility Staff qualifications are being revised to the current ACAD 00-003, Revision 1, eligibility requirements and therefore are acceptable to the NRC.5.0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration Exelon Generation Company, LLC (EGC) and AmerGen Energy Company, LLC (AmerGen)have evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below: 1. Will operation of the facility in accordance with the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.Licensed operator qualification and training can have an indirect impact on accidents previously evaluated.
However, the NRC considered this impact during the rulemaking process, and by promulgation of the revised 10 CFR 55 rule, determined that this impact remains acceptable when licensees have an accredited licensed operator training program which is based on a systems approach to training (SAT). The NRC has concluded in RIS 2001-01 and NUREG-1021 that standards and guidelines applied by INPO in their accredited training programs are equivalent to those put forth by or endorsed by the NRC. Therefore, maintaining an INPO accredited SAT licensed operator training program is equivalent to maintaining an NRC approved licensed operator training program which conforms with applicable NRC Page 2 Attachment 1 Evaluation of Proposed Changes Regulatory Guidelines or NRC endorsed industry standards.
The proposed changes conform to ACAD 00-003, Revision 1 licensed operator education and experience eligibility requirements.
Based on the above, EGC and AmerGen conclude that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2 Will operation of the facility in accordance with the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No.The proposed amendment involves changes to the licensed operator training programs, which are administrative in nature. The EGC and AmerGen licensed operator training programs have been accredited by INPO and are based on SAT.Based on the above discussion, EGC and AmerGen conclude that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Will operation of the facility in accordance with the proposed amendment involve a significant reduction in a margin of safety?Response:
No.The proposed TS changes are administrative in nature. The proposed TS changes do not affect plant design, hardware, system operation, or procedures for accident mitigation systems. The proposed changes do not impact the performance or proficiency requirements for licensed operators.
As a result, the ability of the plant to respond to and mitigate accidents is unchanged by the proposed TS changes. Therefore, these changes do not involve a significant reduction in a margin of safety.Based on the above, EGC and AmerGen conclude that the proposed changes do not involve a significant reduction in a margin of safety.Based on the above evaluation of the three criteria, EGC and AmerGen conclude that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable
Regulatory Requirements/Criteria 10 CFR 50 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities," Section 120,"Training and Qualification of Nuclear Power Plant Personnel," requires that each nuclear power plant licensee or applicant for an operator license implement training and qualification programs that are derived from a systems approach to training.
The proposed license amendment conforms to these requirements.
Page 3 Attachment 1 Evaluation of Proposed Changes 10 CFR 55 10 CFR 55, "Operators' Licenses," Subpart D, "Applications," requires that operator license applications include information concerning an individual's education and experience and other related matters. The proposed license amendment conforms to these requirements.
NUREG-1021, Revision 9 NUREG-1021, "Operator Licensing Examination Standards For Power Reactors," Section ES-202, "Preparing and reviewing Operator Licensing Application," states, in part, that "the fact that every facility licensee has voluntarily obtained and periodically renewed the accreditation of its licensed operator training program suggests that every facility licensee is implementing the education and experience guidelines endorsed by the NNAB. Specifically, the NRC staff has stated that the current version of those guidelines is outlined in the NANT 'Guidelines for Initial Training and Qualification of Licensed Operators,'
which were issued in January 2000 (NANT 2000 guidelines).
Consequently, unless otherwise informed by a facility licensee, the NRC staff has stated that the education and experience guidelines described in the NANT 2000 guidelines constitute the facility licensee's education and experience requirements to be licensed as an RO or SRO." The proposed license amendment conforms to the NANT ACAD 00-003, Revision 1, education and experience eligibility requirements.
Regulatory Guide (RG) 1.8, Revision 3 RG 1.8, "Qualification and Training of Personnel for Nuclear Power Plants," describes a method that the NRC staff finds acceptable for complying with the NRC's regulations with regard to training and qualification of nuclear power plant personnel.
The NRC has reviewed the current education and experience guidelines outlined in the NANT ACAD 00-003, Revision 1, 'Guidelines for Initial Training and Qualifications of Licensed Operators," and concluded that they are equivalent to the NRC staff guidelines in RG 1.8, Revision 3, as discussed in two pre-submittal teleconferences with NRC subject matter experts. The proposed license amendment conforms to the NANT ACAD 00-003, Revision 1, education and experience eligibility requirements.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the NRC's regulations, and (3)the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.6.0 ENVIRONMENTAL CONSIDERATION The proposed amendment does not change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR 20 and does not change surveillance requirements.
The proposed amendment revises Technical Specifications for Facility Staff Qualification education and experience eligibility requirements for reactor and senior reactor operator applicants that will allow for the development of an ILT training program.The proposed amendment does not involve (i) a significant hazards consideration, (ii) a Page 4 Attachment 1 Evaluation of Proposed Changes significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in the individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 PRECEDENT
A similar amendment was approved for Wolf Creek Generating Station on January 31, 2005 (TAC NO. MC4795, ML050340189).
8.0 REFERENCES
- 1. National Academy for Nuclear Training Academy Document 00-003, Revision 1,"Guidelines for Initial Training and Qualification of Licensed Operators," dated April 2004 2. RS-02-100, Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S. NRC,"Revision to Technical Specification Change Request -Clarification of Requirements for Licensed Operator Qualification and Training," dated June 19, 2002 3. Letter from K. A. Ainger (Exelon Generation Company, LLC) to U. S. NRC, "Request for Technical Specifications Changes to Clarify Requirements for Licensed Operator Qualifications and Training," dated August 1, 2001 Page 5 Attachment 2 Proposed Technical Specifications (Marked-Up Pages)Technical Specification Unit Staff Qualification Changes for Braidwood Station, Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station and Three Mile Island Nuclear Station Braidwood Units 1 & 2 TS page 5.3-1 Byron Units 1 & 2 TS page 5.3-1 Clinton TS page 5.0-5 Dresden Units 2 & 3 TS page 5.3-1 La Salle Units 1 & 2 TS page 5.3-1 Oyster Creek TS page 6-2a Peach Bottom Unit 2 TS page 5.0-5 Peach Bottom Unit 3 TS page 5.0-5 Quad Cities Unit 1 & 2 TS page 5.3-1 Three Mile Island Unit 1 TS page 6-3 Facility Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONIROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
l)either the senior health physics supervisor or lead health physicist, shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in Exe on letter -S-02-[>
-9, 20,2), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
IRS-07-078 dated July 19, 2007
-UNITS 1 & 2 5.3- 1 Amendment 125 Facility Staff Qualifications 5.3 5.0 AIY4INISI7RATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
Deither the senior health physics supervisor or lead health physicist, shall meet or exceed the qualifications for 'Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in ExeIon letter 1-I02-_100, dated -u-- !9 2-2), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
RS-07-078, dated July 19, 2007 BYRON -1IThflTh 1 & 2 5.3 -1 Amendment 130 BRN- UNITS I & 2 5.3- 1 Amenximnt 130 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978, with the following exception:
the education and experience eligibility requirements for operator license applicants (described in Exelon letter R9 82 108, dated E- JunR 19, 2002), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
IRS-07-078, dated July 19, 2007]CLINTON 5.0-5 Amendment No. 154 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
- 1) the radiation protection manager shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicantsV (described in Exelon letter RS 02 100, dated June 19, 2002), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
IRS-07-078, dated July 19, 20077 I I Dresden 2 and 3 5.3-1 Amendment No. 194/187 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
- 1) the radiation protection manager shall meet the requirements of"radiation protection manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in Exelon letter-RS--
2 1a...- , dated .u 19, 2002), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
Also, the ANSI N18.1-1971 qualification requirements for "radiation protection technician" may be met by IRS-07-078, dated July 19,2007 either of the following alternatives:
- a. Individuals who have completed the radiation technician training program and have accrued working experience in the specialty; or protection one year of b. Individuals who have completed the radiation protection technician training program, but have not yet accrued one year of working experience in the specialty, who are supervised by on-shift radiation protection supervision who meet the requirements of ANSI N18.1-1971, Section 4.3.2 or Section 4.4.4.LaSalle I and 2 5.3-1 Amendment No. 154/140
- c. A break of at least eight hours should be allowed between work period, including shift turnover time.d. In a, b, and c above, the time required to complete shift turnover is to be counted as break time and is not to be counted as work time.e. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.Any deviation from the above guidelines shall be authorized by the Department Managers, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
The Senior Manager -Operations or an Operations Manager, and the Shift Manager require Senior Reactor Operators licenses.
The licensed Nuclear Plant Operators require a Reactor Operators license.6.2.2.3 Individuals who train the operating staff and those who carry out the health physics and quality assurance function shall have sufficient organizational freedom to be independent of operational pressures, however, they may report to the appropriate manager on site.6.3 Facility Staff Qualifications 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications, with the following exceptions:
- 1) the education and experience eligibility requirements for operator license applicants (described in Exelon letter R602 q00), ttd da.ted 19, 2002), and changes thereto, shall be approved by the NRC and described in an July 19, 2007 applicable station training procedure, and 2) technicians and maintenance personnel who do not meet ANSI/ANS 3.1 of 1978, Section 4.5, are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 (Rev. 1-R, 9/75). Each other member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971 shall meet or exceed the minimum qualifications specified therein, or in the case of radiation protection technicians, they shall have at least one year's continuous experience in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations and shall have been certified by the management position responsible for radiological controls as qualified to perform assigned functions.
This certification must be based on an NRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible supervision that the individual has demonstrated his ability to perform each specified procedure and assigned function with an understanding of its basis and purpose.6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, response and analysis of the plant for transients and accidents.
OYSTER CREEK 6-2a Amendment No.: 134,203,220,226,232 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions described in the UFSAR, with the following exceptions:
- 1) the Manager-Radiation Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants (described in Exelon letter R5-82-188, dated dune 19, 282), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).IRS-07-078, dated July 19, 2007! I PBAPS UNIT 2 5.0-5 Amendment No. 245 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions described in the UFSAR, with the following exceptions:
- 1) the Manager-Radiation Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants (described in Exelon letter> RS-62-18, dated dune 19, 2002), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).RS-07-078, dated July 19, 2007!PBAPS UNIT 3 5.0-5 Amendment No. 249 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
- 1) the radiation protection manager or lead radiation protection technician who shall meet or exceed the qualifications for"Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the education and experience eligibility requirements for operator license applicants, (described in Exelon letter-RS--
-9 02 100, dated ae 19, 2002.), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure.
I IRS-07-078, dated July 19, 2007 Quad Cities I and 2 5.3-1 Amendment No. 208/203 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications, with the following exceptions:
- 1) the education and experience eligibility requirements for operator July718, dae7d license applicants (described in Exelon lette r, , ), and changes jJuly 19, 2007 thereto, shall be approved by the NRC and described in an applicable station training procedure, and 2) individuals who do not meet ANSI/ANS 3.1 of 1978, Section 4.5, are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977. Each radiological controls technician/supervisor shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-I Radiation Controls training program. All radiological controls technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents.
6.4 TRAINING
6.4.1 A training program for the Fire Brigade shall be maintained and shall meet or exceed the requirements of Section 600 of the NFPA Code.6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The director of each department shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the Review and Approval Matrix. Implementing approvals shall be performed at the cognizant manager level or above.6-3 Amendment Nos. 11, 32,55, 77, 92, 128, 131, 132,,139, 171, 207, 212,'218, 241