Letter Sequence Request |
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TAC:ME0979, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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Category:Letter type:L
MONTHYEARL-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-049, Core Operating Limits Report for Operating Cycle 202023-03-30030 March 2023 Core Operating Limits Report for Operating Cycle 20 L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report 2024-01-24
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-10-18018 October 2022 Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022 License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022 Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-22-159, Supplement to a License Amendment Request Revising Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation2022-08-0202 August 2022 Supplement to a License Amendment Request Revising Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis2022-06-0101 June 2022 Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis L-22-053, Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2022-05-16016 May 2022 Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-21-204, Unit 2 - License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-03-30030 March 2022 Unit 2 - License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22035A1222022-02-0404 February 2022 Supplement to Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections L-21-138, License Amendment Request to Correct TS 3.1.7 Change Made by TSTF-5472021-09-15015 September 2021 License Amendment Request to Correct TS 3.1.7 Change Made by TSTF-547 L-21-190, Request for an Amendment to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2021-09-15015 September 2021 Request for an Amendment to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections L-21-068, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation2021-08-29029 August 2021 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation L-20-295, Emergency Plan Amendment Request2021-06-14014 June 2021 Emergency Plan Amendment Request L-21-071, Request for an Amendment to Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR)2021-04-26026 April 2021 Request for an Amendment to Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21106A0202021-04-0707 April 2021 Enclosure a - Evaluation of Proposed Change L-20-240, License Amendment Request to Adopt TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control2021-03-0505 March 2021 License Amendment Request to Adopt TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control L-20-129, Emergency Plan Amendment Request2020-12-28028 December 2020 Emergency Plan Amendment Request ML20324A0892020-12-15015 December 2020 Exemption from Annual Force-on-Force Exercise Requirement of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3.(l)(1) (EPID L-2020-LLE-0171 (COVID-19)) L-20-274, Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits2020-10-30030 October 2020 Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits L-20-223, License Amendment Request to Correct Non-conservative Technical Specification 3.7.4, Atmospheric Dump Valves (Advs)2020-10-13013 October 2020 License Amendment Request to Correct Non-conservative Technical Specification 3.7.4, Atmospheric Dump Valves (Advs) L-20-166, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-20-163, License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications2020-07-27027 July 2020 License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications L-20-165, License Amendment Request - Proposed Change to Operating License Conditions Related to Irradiated Fuel Management Plan (Ifmp) Funding; and Withdrawal of Ifmps2020-07-13013 July 2020 License Amendment Request - Proposed Change to Operating License Conditions Related to Irradiated Fuel Management Plan (Ifmp) Funding; and Withdrawal of Ifmps L-20-188, ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names2020-06-26026 June 2020 ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names ML20177A2732020-06-25025 June 2020 Proposed Revision of Technical Specification (TS) 5.5.5, Steam Generator (SG) Program L-20-151, License Amendment Request to Correct Non-conservative Technical Specifications 3.2 .1, Heat Flux Hot Channel Factor Fa(Z) and 5.6.3, Core Operating Limits Report (COLR)2020-06-23023 June 2020 License Amendment Request to Correct Non-conservative Technical Specifications 3.2 .1, Heat Flux Hot Channel Factor Fa(Z) and 5.6.3, Core Operating Limits Report (COLR) L-19-274, License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-3602020-04-24024 April 2020 License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-360 L-20-009, License Amendment Request - Proposed Change to Technical Specifications Sections 1.1. Definitions, and 5.0 Administrative Controls. for Permanently Defueled Condition2020-02-11011 February 2020 License Amendment Request - Proposed Change to Technical Specifications Sections 1.1. Definitions, and 5.0 Administrative Controls. for Permanently Defueled Condition L-19-213, Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR2019-12-18018 December 2019 Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR L-19-265, License Amendment Request to Extend Refueling Special Lifting Devices' Interval for Testing to Verify Continuing Compliance2019-12-18018 December 2019 License Amendment Request to Extend Refueling Special Lifting Devices' Interval for Testing to Verify Continuing Compliance L-19-233, License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-11-14014 November 2019 License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b L-19-099, License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (Vftp), and 5.5.14, Control Room Envelope.2019-10-20020 October 2019 License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (Vftp), and 5.5.14, Control Room Envelope. L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition2019-02-27027 February 2019 Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan2019-02-0505 February 2019 License Amendment Request - Proposed Post-Shutdown Emergency Plan L-18-242, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition2019-02-0505 February 2019 License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2018-10-22022 October 2018 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition L-18-203, Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2018-08-23023 August 2018 Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement 2024-01-24
[Table view] Category:Technical Specifications
MONTHYEARML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21361A2172021-12-20020 December 2021 Supplemental Information for Revision 22 to Updated Safety Analysis Report, Revision 13 to Technical Specification Bases TS Bases ML21334A0302021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21307A1762021-10-28028 October 2021 2 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20335A0522021-02-18018 February 2021 Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition ML21027A2282021-01-27027 January 2021 License Amendment Request for One-time Deferral of Steam Generator Inspections ML20335A1292020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications L-20-298, Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-11-0909 November 2020 Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition ML20280A8272020-11-0303 November 2020 Issuance of Amendment No. 301 to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications ML20213C7262020-08-24024 August 2020 Issuance of Amendment No. 300 to Revise the Containment Leakage Rate Testing Program ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML20160A0742020-05-20020 May 2020 2 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 ML18022B1162018-03-0101 March 2018 Issuance of Amendment Nos. 302 and 191 Regarding the Use of Optimized Zirlo Fuel Rod Cladding (CAC Nos. MF9580 and MF9581; EPID L-2017-LLA-0201) ML17291A0812018-01-22022 January 2018 Issuance of Amendments Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17305A2132017-10-23023 October 2017 Perry Nuclear Power Plant Revision 20 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML17216A5702017-10-12012 October 2017 Issuance of Amendments Emergency Action Level Scheme Changed Based on NEI 99-01, Revision 6 (CAC Nos. MF8448 and MF8449; EPID L-2016-LLA-0011) ML17221A2802017-08-16016 August 2017 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 ML16342C9462017-01-12012 January 2017 Issuance of Amendment Revising Emergency Action Level Scheme ML16040A0842016-06-0707 June 2016 FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications ML16083A4812016-04-27027 April 2016 Issuance of Amendment Revising Emergency Diesel Generator Minimum Voltage and Frequency Acceptance Criteria ML15307A3492016-02-23023 February 2016 Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106) ML15294A4392015-12-16016 December 2015 Issuance of Amendments License Amendment Request to Revise Steam Generator Technical Specifications (CAC Nos. MF6054 and 6055) ML15251A0462015-10-20020 October 2015 Issuance of Amendment Revising Containment Spray Nozzle Surveillance Requirement ML15243A1532015-09-0202 September 2015 Correction of Typographical Error Incurred During Prior License Amendment No. 162 ML15201A5292015-08-17017 August 2015 Issuance of Amendment Concerning Technical Specification 3.8.4 DC Sources - Operating (TAC No. MF5298) (L-14-271) ML15160A0282015-06-23023 June 2015 Issuance of Amendment Concerning Adoption of TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TAC No. MF4791)(L-14-137) ML15141A4822015-06-12012 June 2015 Issuance of Amendment Concerning Changes to Pressure Temperature Curves (TAC No. MF4351)(L-14-150) ML15133A5022015-06-10010 June 2015 Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) ML15086A2512015-05-20020 May 2015 Issuance of Amendment Revise Technical Specification 4.3.2, Spent Fuel Storage Minimum Inadvertent Drainage Elevation L-15-026, License Amendment Request to Steam Generator Technical Specifications2015-04-0101 April 2015 License Amendment Request to Steam Generator Technical Specifications ML14322A4612015-03-0606 March 2015 Issuance of Amendments Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5b. L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014 Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program L-14-300, Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler 4252014-09-21021 September 2014 Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler 425 ML14245A1512014-09-17017 September 2014 Issuance of Amendments Regarding Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013 License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6.. L-12-271, License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions2012-07-25025 July 2012 License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions 2023-10-02
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FENOC 76 South Main Street FirstEnergy Nuclear Operating Company Akron, Ohio 44308 Joseph J. Hagan 330-761- 7895 President and Chief Nuclear Officer F a : 330-384-3799 March 25, 2009 L-09-025 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Davis-Besse Independent Spent Fuel Storage Installation Docket No. 72-14, License No. NPF-3 Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Workina Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 In accordance with the provisions of 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications for the Beaver Valley Power Station Unit Nos. 1 and 2, the Davis-Besse Nuclear Power Station, and the Perry Nuclear Power Plant.
The proposed amendment would delete those portions of Technical Specifications superseded by 10 CFR Part 26, Subpart I. The enclosure provides the evaluation for the proposed amendment.
Approval of the license amendment is requested prior to September 30, 2009. Removal of the plant-specific Technical Specification requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.
Beaver Valley Power Station Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station Perry Nuclear Power Plant L-09-025 Page 2 of 2 Regulatory commitments associated with this submittal are included in the attachment.
If there are any questions, or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March a<, 2009.
Sincere1y , I Joseph J. Ha Attachment :
Regulatory Commitment List
Enclosure:
Evaluation of Proposed Change cc: NRC Region I Administrator NRC Region Ill Administrator NRC Resident Inspector (Beaver Valley)
NRC Resident Inspector (Davis-Besse)
NRC Resident Inspector (Perry)
NRR Project Manager (Beaver Valley)
NRR Project Manager (Davis-Besse)
NRR Project Manager (Perry)
Director BRP/DEP Site BRP/DEP Representative Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Attachment L-09-025 Regulatory Commitment List Page 1 of 1 The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Beaver Valley Power Station Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant in this document.
Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not Regulatory Commitments.
Please notify Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071 of any questions regarding this document or associated Regulatory Commitments.
Renulatow Commitment Due Date
- 1. Removal of the plant-specific Technical This commitment will be Specification requirements will be performed completed no later than October 1, concurrently with the implementation of the 2009.
10 CFR Part 26, Subpart I requirements.
E\ I1 ation of Proposed Change Page 1 of 6
Subject:
Application for Technical Specification (TS) Change for Adoption of TSTF-51 1, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2to Support Compliance with 10 CFR Part 26 1.O DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Determination 5.2 A ppIicable Regulatory Requirements/C riteria
6.0 ENVIRONMENTAL CONSIDERATION
7.0 REFERENCES
Attachments
- 1. Proposed Technical Specification Changes (Mark-Up)
- 2. Proposed Technical Specification Changes (Re-Typed)
Page 2 of 6
1.0 DESCRIPTION
The proposed amendment would delete those portions of Technical Specifications (TS) superseded by 10 CFR Part 26, Subpart 1. This change is consistent with Nuclear Regulatory Commission (NRC) approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-51I, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. Minor differences between the proposed plant specific TS changes, and the changes proposed by TSTF-511 are listed in Section 2.0. The availability of this TS improvement was announced in the Federal Register on December 30,2008 (73 FR 79923) as part of the consolidated line item improvement process (CLIIP).
2.0 PROPOSED CHANGE
Consistent with the NRC approved Revision 0 of TSTF-511, the proposed TS changes delete those portions of TS superseded by 10 CFR Part 26, Subpart I.
This application is being made in accordance with the CLIIP. FirstEnergy Nuclear Operating Company (FENOC) is proposing the following minor deviations from the TS changes described in TSTF-511, Revision 0. These deviations are administrative and do not affect the applicability of the proposed change.
- 1. Requirements to be removed from TS will be marked Deleted and subsequent requirements will not be renumbered.
- 2. Requirements for working hour restrictions are located in paragraph e of Perry Nuclear Power Plant TS 5.2.2 rather than paragraph d of TS 5.2.2 as indicated in TSTF-511, Revision 0. Therefore, the portion of Perry Nuclear Power Plant TS superseded by 10 CFR Part 26, Subpart I, is TS 5.2.2.e.
TS 5.2.2.e will be deleted from Perry Nuclear Power Plant TS.
- 3. Perry Nuclear Power Plant TS requirements 5.2.2.f and 5.2.2.g will be moved from TS page 5.0-3a to TS page 5.0-3, and page 5.0-3a will be removed from the TS.
FENOC is not proposing any other variations or deviations from the NRC staffs model safety evaluation (SE) published on December 30,2008 (73 FR 79923) as part of the CLllP Notice of Availability.
3.0 BACKGROUND
The NRC issued a Federal Reaisfer notice (73 FR 16966, March 31, 2008) of the issuance of a final rule that amended I O CFR Part 26. The revised regulations in 10 CFR Part 26, Subpart I supersede working hour restrictions contained in paragraph d of TS 5.2.2 for Beaver Valley Power Station Unit Nos. 1 and 2 (DPR-66 and NPF-73) and Davis-Besse Nuclear Power Station (NPF-3) and paragraph e of TS 5.2.2 for Perry
Page 3 of 6 Nuclear Power Plant (NPF-58). The background for this application is adequately addressed by the NRC Notice of Availability published on December 30, 2008 (73 FR 79923).
4.0 TECHNICAL ANALYSIS
FENOC has reviewed the SE published on December 30,2008 (73 FR 79923) as part of the CLllP Notice of Availability. FENOC has concluded that the technical justifications presented in the SE prepared by the NRC staff are applicable to Beaver Valley Power Station Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant.
10 CFR Part 26, Subpart I, supersedes existing worker fatigue guidance. 10 CFR Part 26, Subpart I, distinguishes between work hour controls and fatigue management and strengthens the requirements for both. Under the new rule, work hour restrictions include not only work hour limitations for rolling 24-hour, 48-hour, and 7-day periods, but also include a required minimum break between work periods and varying required minimum days off. Additionally, Subpart I confines the use of waivers (deviations from restrictions) to situations where overtime is necessary to mitigate or prevent a condition adverse to safety or necessary to maintain the security of the facility. Subpart 1 also strengthens reporting requirements. Finally, the new rules work hour control scope includes certain operating and maintenance personnel, as well as individuals directing those operating and maintenance personnel, health physics and chemistry personnel who are a part of the on-site emergency response organization minimum shift complement, the fire brigade member who is responsible for understanding the effects of fire and fire suppressants on safe shutdown capability, and certain security personnel.
The proposed change removes working hour limits imposed in the Technical Specifications in order to support compliance with 10 CFR Part 26, Subpart I. Work hour controls and fatigue management requirements have been incorporated into the NRCs regulations; therefore, it is unnecessary to have work hour control requirements in the Technical Specifications.
Removal of the Technical Specification requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I, requirements, even if the Technical Specification change is implemented prior to the October 1, 2009 deadline.
Along with this license amendment request (LAR), FENOC has submitted a commitment to comply with 10 CFR Part 26 concurrently with the implementation of the Technical Specification change.
Page 4 of 6 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Siqnificant Hazards Determination FENOC has reviewed the no significant hazards determination published on December 30, 2008 (73 FR 79923) as part of the CLllP Notice of Availability. FENOC has concluded that the determination presented in the notice is applicable to Beaver Valley Power Station Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant. FENOC has evaluated the proposed changes to the TS using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration. An analysis of the issue of no significant hazards consideration is presented below:
Criterion I:The Proposed Change Does Not Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated The proposed change removes Technical Specification restrictions on working hours for personnel who perform safety related functions. The Technical Specification restrictions are superseded by the worker fatigue requirements in 10 CFR Part 26. Removal of the Technical Specification requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I, requirements. The proposed change does not impact the physical configuration or function of plant structures, systems, or components (SSCs) or the manner in which SSCs are operated, maintained, modified, tested, or inspected. Worker fatigue is not an initiator of any accident previously evaluated. Worker fatigue is not an assumption in the consequence mitigation of any accident previously evaluated.
Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2: The Proposed Change Does Not Create the Possibility of a New or Different Kind of Accident From Any Accident Previously Evaluated The proposed change removes Technical Specification restrictions on working hours for personnel who perform safety related functions. The Technical Specification restrictions are superseded by the worker fatigue requirements in 10 CFR Part 26. Working hours will continue to be controlled in accordance with NRC requirements. The new rule allows for deviations from controls to mitigate or prevent a condition adverse to safety or as necessary to maintain the security of the facility. This ensures that the new rule will not unnecessarily restrict working hours and thereby create the possibility of a new or different kind of accident from any accident previously evaluated.
Page 5 of 6 The proposed change does not alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, or effect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Criterion 3: The Proposed Change Does Not Involve a Significant Reduction in a Margin of Safety The proposed change removes Technical Specification restrictions on working hours for personnel who perform safety related functions. The Technical Specification restrictions are superseded by the worker fatigue requirements in 10 CFR Part 26. The proposed change does not involve any physical changes to the plant or alter the manner in which plant systems are operated, maintained, modified, tested, or inspected. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed change will not result in plant operation in a configuration outside the design basis. The proposed change does not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
Removal of plant-specific Technical Specificat ion administrative requirements will not reduce a margin of safety because the requirements in 10 CFR Part 26 are adequate to ensure that worker fatigue is managed.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, FENOC concludes that the proposed change 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 Ap pIicable Regulatory Reauirements/C riteria A description of the proposed TS change and its relationship to applicable regulatory requirements was provided in the NRC Notice of Availability published on December 30,2008 (73 FR 79923). FENOC has reviewed the NRC staffs model SE published on December 30, 2008 (73 FR 79923) as part of the CLllP Notice of Availability and concluded that the regulatory evaluation section is applicable to Beaver Valley Power Station Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant.
Page 6 of 6 The proposed change eliminates the plant-specific Technical Specification administrative controls on working hours. The Technical Specification guidance has been superseded by 10 CFR Part 26.
10 CFR Part 26, Subpart I,Managing Fatigue, contains requirements for managing worker fatigue at operating nuclear power plants.
10 CFR 50.36 provides, among other things, the regulatory requirements for the content in the Administrative Controls section of the Technical Specifications. The inclusion of requirements to control working hours and manage fatigue is not required to be in the Administrative Controls by 10 CFR Part 50.36. Because the requirement to control working hours and manage fatigue is provided in 10 CFR Part 26, Subpart I, it is unnecessary for the Technical Specifications to contain similar controls.
6.0 ENVIRONMENTAL CONSIDERATION
FENOC has reviewed the environmental evaluation included in the SE published on December 30, 2008 (73 FR 79923) as part of the CLllP Notice of Availability. FENOC has concluded that the staffs findings presented in that evaluation are applicable to Beaver Valley Power Station Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant. The proposed amendment changes recordkeeping, reporting, or administrative procedures. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)( IO). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 REFERENCES
- 1. Federal Register Notice, Final Rule 10 CFR Part 26 published on March 31, 2008 (73 FR 16966).
- 2. TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.
- 3. Federal Register Notice, Notice of Availability published on December 30, 2008 (73 FR 79923).
Page 1 of 7 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.I Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management tevsls, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the Unit 2 UFSAR,
- b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant, C. A corporate officer with direct responsibility fur the plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety, and
- d. The individuals who train the operating staff, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Unit Staff The unit staff organization shall include the following:
- a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES I, 2, 3, or 4.
- b. Shift crew composition may be less than the minimum requirement of I O CFR 50.54(rn)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
Beaver Valley Units 1 and 2 -
5.2 1 Amendments 278 / 161
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
C. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. The operations manager shall either hold an SRO license or have held an SRO license for a pressurized water reactor. The assistant operations manager shall hold a current SRO license.
- f. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. A single qualified person can be used to satisfy this position for both units.
Beaver Valley Units 1 and 2 -
5.2 2 Amendments 2?&/ +&I=
Urganization 5.2 5.0 ADMINISTRATtVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
- a. Lines of authority, responsibildy, and communicationshall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the UFSAR.
- b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
C. A specified corporate officer shall have corporate responsibility for Overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Unit Staff The unit staff organization shall include the following:
- a. A non-licensed operator shalt be assigned if the reactor contains fuel and an additional non-licensed operator shall be assigned if the reactor is operating in MODES 1, 2, 3, or 4;
- b. Shift crew composition may be less than the minimum requirement of I O CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence Of on-duty shift crew members provided immediate action is taken to restore the shift crew compositionto within the minimum requirements; Davis-Besse 5.2-1 Amendment 279
Organization 5.2 5.2 Organization 5.2.2 unit Staff (continued)
C. A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpectedabsence, provided immediate action is taken to fill the required position;
- e. The operations manager shall either hold or have held a Senior Operator license. The assistant operations manager shall hold a Senior Operator license for the Davis-Besse Nuclear Power Station; and
- f. When the reactor is operating in MODE 1, 2, 3, or 4 an individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shafl meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Davis-Besse 5.2-2 Amendment 2W-
Organization 5.2 5.2 Organ1zation (continued1 5.2.2 yn1t S t a f f The unit s t a f f organlzation shall include the fol1owlng:
A non-licensed operator shall be on site when fuel i s i n the reactor vessel. and an additional non-1 icensed OperatUr shalt be on site whlle the unit Is i n MODE 1, 2, or 3;
- b. Deleted -ce
- c. Shift crew composition m a y be one less than the minimm
. requirements o f 10 CFR 50,54(m)(2)(i> and Specifications 5.2.2.a and 5.2.2.g for a erlod o f tlme not
!
t o exceed two hours i n order t o accomda e unexpected absence o f on-duty s h i f t crew members, provided Immediate action i s taken t o restore the s h i f t crew composition t o w i t h i n the minimum requirements.
- d. A radiation protection technician shall be on slte when fuel 1s i n the reactor, The position may be vacant f o r not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, i n order t o provide f o r unexpected absence, provided inmediate action i s taken t o f i l l the required posltion.
(contif nued 1 PERRY - UNIT 1 5.0-3 Amendment No .*
5.2 orgrtnlzation v -
- 5. Ma
Page 1 of 4 PROPOSED TECHNICAL SPECIFICATION CHANGES (RE-TYPED)
0rganization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- e. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- d. Deleted. I
- e. The operations manager shall either hold an SRO license or have held an SRO license for a pressurized water reactor. The assistant operations manager shall hold a current SRO license.
- f. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift, A single qualified person can be used to satisfy this position for both units.
Beaver Valley Units 1 and 2 5.2 - 2 Amendments I
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- c. A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;
- d. Deleted; I
- e. The operations manager shall either hold or have held a Senior Operator license. The assistant operations manager shall hold a Senior Operator license for the Davis-Besse Nuclear Power Station; and
- f. When the reactor is operating in MODE 1, 2, 3, or 4 an individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Davis-Besse 5.2-2 Amendment
Organization 5.2 5.2 Organization (continued)
__ - ~-~ . .
5.2.2 Unit S t a f f The u n i t s t a f f organization shall include the following:
- a. A non-licensed operator shall be on s i t e when fuel i s i n the reactor vessel, and an additional non-licensed operator shall be on site while the u n i t i s i n MODE 1, 2, o r 3.
- b. Deleted C. Shift crew composition may be one less than the minimum requirements o f 10 CFR 50.54(rn)(Z)(i) and Specifications 5.2.2.a and 5.2.2.g f o r a period o f time not t o exceed two hours i n order t o accommodate unexpected absence o f on-duty s h i f t crew members, provided immediate action i s taken t o restore the s h i f t crew composition t o w i t h i n the minimum requi rements .
- d. A radiation protection technician shall be on s i t e when fuel i s i n the reactor. The position may be vacant f o r not NOR than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, i n order t o provide f o r unexpected absence, provided imnediate action i s taken t o f i l l the required position.
- e. Deleted I
- f. The operations manager or a t least one operations middle manager shall hold an SRO license.
g- The s h i f t technical advisor (STA) shall provide advisory technical support t o the s h i f t supervisor ( S S ) in the areas K
of thermal h draulics, reactor engineering, and plant analysis w i t regard t o the safe operatlon o f the unit, In addition, the STA shall meet the qualifications specified by the Commission Polic Statement on Engineering Ex ertise I f:
on s h i f t . The STA posi ion may be f i l l e d by an on-s ift SS or SRO provided the individual meets the Commission Policy Statement on Engineeri ng Expert ise on s h i f t .
PERRY - UNIT 1 5.0-3 Amendment No.
March 25, 2009 L-09-025 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Davis-Besse Independent Spent Fuel Storage Installation Docket No. 72-14, License No. NPF-3 Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Application for Technical Specification (TS) Change for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 In accordance with the provisions of 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications for the Beaver Valley Power Station Unit Nos. 1 and 2, the Davis-Besse Nuclear Power Station, and the Perry Nuclear Power Plant.
The proposed amendment would delete those portions of Technical Specifications superseded by 10 CFR Part 26, Subpart I. The enclosure provides the evaluation for the proposed amendment.
Approval of the license amendment is requested prior to September 30, 2009. Removal of the plant-specific Technical Specification requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.
Beaver Valley Power Station Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station Perry Nuclear Power Plant L-09-025 Page 2 of 2 Regulatory commitments associated with this submittal are included in the attachment.
If there are any questions, or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March ___, 2009.
Sincerely, Joseph J. Hagan
Attachment:
Regulatory Commitment List
Enclosure:
Evaluation of Proposed Change cc: NRC Region I Administrator NRC Region III Administrator NRC Resident Inspector (Beaver Valley)
NRC Resident Inspector (Davis-Besse)
NRC Resident Inspector (Perry)
NRR Project Manager (Beaver Valley)
NRR Project Manager (Davis-Besse)
NRR Project Manager (Perry)
Director BRP/DEP Site BRP/DEP Representative Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board