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Category:Letter type:L
MONTHYEARL-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-23-229, 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-23-227, 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-23-208, 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-23-172, 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-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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-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-23-065, 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-23-132, 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-23-115, 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-23-126, 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-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair 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-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023 Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H 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-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022 Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022 Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022 Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022 Request for Fire Protection Program Changes 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-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022 Spent Fuel Storage Cask Registration 2023-09-14
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-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 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-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-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-22-053, 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) 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-20-163, 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-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-19-099, 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 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-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 L-18-081, Steam Generator Technical Specification Amendment Request2018-03-28028 March 2018 Steam Generator Technical Specification Amendment Request L-17-292, Modified Rt PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule2017-10-0606 October 2017 Modified Rt PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule L-17-275, Supplement to Request for Licensing Action to Revise the Emergency Plan2017-09-0707 September 2017 Supplement to Request for Licensing Action to Revise the Emergency Plan L-17-223, Application to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1, Clarification of Rod Position Requirements.2017-06-30030 June 2017 Application to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1, Clarification of Rod Position Requirements. L-17-159, Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2017-05-18018 May 2017 Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement L-17-111, License Amendment Request to Modify Technical Specifications 4.2.1 and 5.6.3 and a 10 CFR 50.12 Exemption Request to Implement Optimized Zirlo Fuel Rod Cladding2017-04-0909 April 2017 License Amendment Request to Modify Technical Specifications 4.2.1 and 5.6.3 and a 10 CFR 50.12 Exemption Request to Implement Optimized Zirlo Fuel Rod Cladding L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016 Supplement to Request for License Amendment Approval Delay L-16-163, Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments2016-06-24024 June 2016 Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments L-15-341, License Amendment Request to Modify Technical Specifications 5.3.12015-11-19019 November 2015 License Amendment Request to Modify Technical Specifications 5.3.1 L-15-026, License Amendment Request to Steam Generator Technical Specifications2015-04-0101 April 2015 License Amendment Request to Steam Generator Technical Specifications L-14-166, Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation2014-06-0202 June 2014 Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation L-14-121, License Amendment Request to Extend Containment Leakage Test Frequency2014-04-16016 April 2014 License Amendment Request to Extend Containment Leakage Test Frequency L-13-223, License Amendment Request to Implement 10 CFR 50.61a. Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.2013-07-30030 July 2013 License Amendment Request to Implement 10 CFR 50.61a. Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events. L-12-397, Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest2013-02-19019 February 2013 Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest 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 ML1126402462011-09-20020 September 2011 License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC L-11-141, License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System2011-05-27027 May 2011 License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System L-10-275, License Amendment Request for Spent Fuel Pool Rerack2010-10-18018 October 2010 License Amendment Request for Spent Fuel Pool Rerack L-10-063, License Amendment Request No. 09-005, Revised Steam Generator Inspection Scope2010-02-26026 February 2010 License Amendment Request No. 09-005, Revised Steam Generator Inspection Scope L-09-141, Application to Permit Operation with Astrum Best-Estimate Large Break Loss of Coolant Accident (LOCA) Methodology2009-07-0606 July 2009 Application to Permit Operation with Astrum Best-Estimate Large Break Loss of Coolant Accident (LOCA) Methodology L-09-096, License Amendment Request No. 08-008, Elimination of Recirculation Spray Pump Response Time Surveillance Requirement2009-06-11011 June 2009 License Amendment Request No. 08-008, Elimination of Recirculation Spray Pump Response Time Surveillance Requirement L-09-138, License Renewal Application, Amendment No. 362009-05-14014 May 2009 License Renewal Application, Amendment No. 36 2023-09-12
[Table view] Category:Technical Specification
MONTHYEARML23144A3072023-05-23023 May 2023 Technical Specification Bases Update Status, Revision 47 L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair 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-22-159, 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 ML22144A1272022-05-18018 May 2022 Rev. 43 to Technical Specification Bases ML22035A1222022-02-0404 February 2022 Supplement to Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML21334A0342021-11-22022 November 2021 Technical Specifications Bases Update Status, Revision 41 L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-10-19019 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements 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) ML20335A1422020-11-23023 November 2020 8 to Technical Specification Bases Update Status ML20177A2732020-06-25025 June 2020 Proposed Revision of Technical Specification (TS) 5.5.5, Steam Generator (SG) Program ML20160A0792020-05-20020 May 2020 Technical Specification Bases Update Status, Revision 37 (Part 1 of 2) 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-18-081, Steam Generator Technical Specification Amendment Request2018-03-28028 March 2018 Steam Generator Technical Specification Amendment Request L-17-108, Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules2017-08-11011 August 2017 Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules ML17117A4592017-04-21021 April 2017 Technical Specification Bases Update Status, Rev. 32 ML14339A4522014-11-24024 November 2014 Technical Specification Bases Update Status, Revision 27 L-14-166, Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation2014-06-0202 June 2014 Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation L-13-359, End-of-Life Moderator Temperature Coefficient Testing Revision2013-11-14014 November 2013 End-of-Life Moderator Temperature Coefficient Testing Revision ML11284A1872011-10-25025 October 2011 Issuance of Amendment Regarding the Adoption of Technical Specifications Task Force Change Traveler-513, Revise PWR Operability Requirements and Actions for Reactor Coolant System Leakage Instrumentation L-09-141, Application to Permit Operation with Astrum Best-Estimate Large Break Loss of Coolant Accident (LOCA) Methodology2009-07-0606 July 2009 Application to Permit Operation with Astrum Best-Estimate Large Break Loss of Coolant Accident (LOCA) Methodology L-09-086, License Amendment Request No. 08-027, Spent Fuel Pool Rerack2009-04-0909 April 2009 License Amendment Request No. 08-027, Spent Fuel Pool Rerack L-08-307, License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving2008-10-10010 October 2008 License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving L-07-106, License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving2007-09-19019 September 2007 License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving L-07-115, Core Operating Limits Report, COLR 18-42007-08-29029 August 2007 Core Operating Limits Report, COLR 18-4 ML0718300332007-04-30030 April 2007 Technical Specification, Correction to Facility Operating License (OL) Page 6A for Unit 1 ML0718300302007-04-26026 April 2007 Technical Specifications, Typographical Errors Were Inadvertently Introduced on Operating License (OL) Page 6a for Unit 1 and OL Page 6 for Unit 2 L-07-010, License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments2007-02-0101 February 2007 License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments L-06-149, Improved Technical Specification (ITS) Conversion License Amendment Request2006-10-24024 October 2006 Improved Technical Specification (ITS) Conversion License Amendment Request L-06-132, Supplement to License Amendment Request No. 183 - Submittal of Final Proposed Technical Specification Changes2006-09-0101 September 2006 Supplement to License Amendment Request No. 183 - Submittal of Final Proposed Technical Specification Changes ML0604504002006-02-0909 February 2006 Tech Spec for Beaver Valley, Unit 1 - Issuance of License Amendment 273 Steam Generator (SG) Replacement L-05-198, Supplemental Information for License Amendment Request2005-12-16016 December 2005 Supplemental Information for License Amendment Request L-05-168, Supplement to License Amendment Request2005-10-28028 October 2005 Supplement to License Amendment Request ML0526902352005-09-19019 September 2005 Technical Specifications Amendment for Beaver Valley, Units 1 and 2 L-05-141, Supplement to License Amendment Request Nos. 306 & 176 Emergency Diesel Generator Allowed Outage Time Extension2005-08-15015 August 2005 Supplement to License Amendment Request Nos. 306 & 176 Emergency Diesel Generator Allowed Outage Time Extension L-05-061, License Amendment Request No. 183 Revised Steam Generator Inspection Scope2005-04-11011 April 2005 License Amendment Request No. 183 Revised Steam Generator Inspection Scope ML0508704912005-03-24024 March 2005 Technical Specification Pages Re Elimination of Periodic Pressure Sensor & Protection Channel Response Time Testing ML0507503442005-03-11011 March 2005 Technical Specification Pages Re Overpressure Protection System (Opps) Enable Temperature, Residual Heat Removal (RHR) System Surveillance, and Miscellaneous and Administrative Changes L-05-009, License Amendment Request Nos. 310 and 1822005-02-11011 February 2005 License Amendment Request Nos. 310 and 182 L-04-127, License Amendment Request Nos. 327 and 197 on Steam Generator Level Allowable Value Setpoints2004-10-0505 October 2004 License Amendment Request Nos. 327 and 197 on Steam Generator Level Allowable Value Setpoints L-04-124, License Amendment Request Nos. 318 and 1912004-10-0404 October 2004 License Amendment Request Nos. 318 and 191 L-04-094, License Amendment Request No. 1842004-07-23023 July 2004 License Amendment Request No. 184 L-04-074, License Amendment Request Nos. 326 and 1772004-06-0101 June 2004 License Amendment Request Nos. 326 and 177 ML0414501122004-05-19019 May 2004 Unit, 1 and 2 - Tech Spec Pages for License Amendments 259 & 142 Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors ML0414501162004-05-19019 May 2004 Unit, 1 and 2, Tech Spec Pages for License Amendments 259 & 142 Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors L-04-041, Technical Specification Bases Change Submittal2004-03-23023 March 2004 Technical Specification Bases Change Submittal ML0409302052004-03-23023 March 2004 Technical Specification Bases Change Submittal, Technical Specification Bases Update Status, Section B-I, Change No. 013-Section B 3/4 10-1 Amendment No. 2 ML0409302102004-03-23023 March 2004 Technical Specification Bases Change Submittal, Technical Specification Bases Update Status, Section B-I Change No. 2-017-Section B 3/4 10-1 Change No. 2-001 L-04-040, License Amendment Request Nos. 321 and 193, Modifying Technical Specification Requirements for Mode Change Limitations in Specifications 3.0.4 and 4.0.4 and the Associated Technical Specification Bases2004-03-22022 March 2004 License Amendment Request Nos. 321 and 193, Modifying Technical Specification Requirements for Mode Change Limitations in Specifications 3.0.4 and 4.0.4 and the Associated Technical Specification Bases L-03-146, License Amendment Request Nos. 315 and 1882003-10-17017 October 2003 License Amendment Request Nos. 315 and 188 2023-05-23
[Table view] Category:Bases Change
MONTHYEARML23144A3072023-05-23023 May 2023 Technical Specification Bases Update Status, Revision 47 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 ML22144A1272022-05-18018 May 2022 Rev. 43 to Technical Specification Bases ML21334A0342021-11-22022 November 2021 Technical Specifications Bases Update Status, Revision 41 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) ML20335A1422020-11-23023 November 2020 8 to Technical Specification Bases Update Status ML20177A2732020-06-25025 June 2020 Proposed Revision of Technical Specification (TS) 5.5.5, Steam Generator (SG) Program ML20160A0792020-05-20020 May 2020 Technical Specification Bases Update Status, Revision 37 (Part 1 of 2) 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-18-081, Steam Generator Technical Specification Amendment Request2018-03-28028 March 2018 Steam Generator Technical Specification Amendment Request ML17117A4592017-04-21021 April 2017 Technical Specification Bases Update Status, Rev. 32 ML14339A4522014-11-24024 November 2014 Technical Specification Bases Update Status, Revision 27 L-14-166, Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation2014-06-0202 June 2014 Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation L-13-359, End-of-Life Moderator Temperature Coefficient Testing Revision2013-11-14014 November 2013 End-of-Life Moderator Temperature Coefficient Testing Revision L-06-132, Supplement to License Amendment Request No. 183 - Submittal of Final Proposed Technical Specification Changes2006-09-0101 September 2006 Supplement to License Amendment Request No. 183 - Submittal of Final Proposed Technical Specification Changes L-05-198, Supplemental Information for License Amendment Request2005-12-16016 December 2005 Supplemental Information for License Amendment Request L-05-168, Supplement to License Amendment Request2005-10-28028 October 2005 Supplement to License Amendment Request L-05-141, Supplement to License Amendment Request Nos. 306 & 176 Emergency Diesel Generator Allowed Outage Time Extension2005-08-15015 August 2005 Supplement to License Amendment Request Nos. 306 & 176 Emergency Diesel Generator Allowed Outage Time Extension L-05-009, License Amendment Request Nos. 310 and 1822005-02-11011 February 2005 License Amendment Request Nos. 310 and 182 L-04-074, License Amendment Request Nos. 326 and 1772004-06-0101 June 2004 License Amendment Request Nos. 326 and 177 ML0409302102004-03-23023 March 2004 Technical Specification Bases Change Submittal, Technical Specification Bases Update Status, Section B-I Change No. 2-017-Section B 3/4 10-1 Change No. 2-001 L-04-041, Technical Specification Bases Change Submittal2004-03-23023 March 2004 Technical Specification Bases Change Submittal ML0409302052004-03-23023 March 2004 Technical Specification Bases Change Submittal, Technical Specification Bases Update Status, Section B-I, Change No. 013-Section B 3/4 10-1 Amendment No. 2 ML0216202982002-06-0505 June 2002 License Amendment Request Nos 300 & 172 ML0212304952002-04-19019 April 2002 Technical Specification Bases Update Status 2023-05-23
[Table view] |
Text
FENOCTM FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President June 2, 2014 L-14-166 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 BV-2 Docket No. 50-412, License No. NPF-73 Revise Technical Specification 4.3.2, 10 CFR 50.90 Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Pursuant to 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) hereby requests an amendment to the operating license for Beaver Valley Power Station, Unit No. 2 (BVPS-2).
The proposed amendment is required to correct the minimum drain elevation for the spent fuel storage pool specified in Technical Specification 4.3.2. In accordance with 10 CFR 50, Appendix B, Section XVI, "Corrective Action," and the FENOC Corrective Action Program, this proposed amendment is required to resolve a Technical Specification discrepancy regarding an existing plant design feature and is not a voluntary request from a licensee to change its licensing basis. The FENOC evaluation of the proposed amendment is enclosed.
FENOC requests approval of the proposed amendment by June of 2015. There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Fleet Licensing, at 330-315-6810.
I declare under penalty of perjury that the foregoing is true and correct. Executed on June _2_, 2014. Sincerely, Eric A. Larson Beaver Valley Power Station, Unit No. 2 L-14-166 Page2
Enclosure:
FENOC Evaluation of Proposed Amendment cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative Evaluation of the Proposed Amendment Page 1 of 9
Subject:
License Amendment Application to Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation.
1.0
SUMMARY
DESCRIPTION
2.0 DETAILED
DESCRIPTION
3.0 TECHNICAL
EVALUATION
4.0 REGULATORY EVALUATION
4.1 Significant
Hazards Consideration
4.2 Applicable
Regulatory Requirements/Criteria
4.3 Conclusion
5.0 ENVIRONMENTAL
CONSIDERATION Attachments:
- 1. Proposed Technical Specification Change (Mark-Up)
- 2. Retyped Technical Specification Page Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 2 of 9 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to change a Technical Specification contained in Appendix A to Operating License NPF-73 for Beaver Valley Power Station, Unit No.2 (BVPS-2).
Design Feature 4.3.2, "Drainage," requires that the spent fuel storage pool be designed to prevent inadvertent draining of the pool below a certain specified elevation.
The proposed change would revise this specified elevation to reflect the installed piping by lowering the elevation 5 inches. 2.0 DETAILED DESCRIPTION During a review of operating experience FirstEnergy Nuclear Operating Company identified a discrepancy.
Based on plant drawings, the spent fuel storage pool cooling pump suction piping passes through the spent fuel storage pool liner wall at a pipe centerline elevation of 751 feet, 3 inches. The nominal inner diameter of the pipe is 10 inches; therefore, the lowest elevation of the inside diameter of this pipe where it enters the spent fuel storage pool is 750 feet, 10 inches. Elevation 750 feet, 10 inches is lower than the minimum inadvertent drainage elevation currently specified for the spent fuel storage pool in Technical Specification 4.3.2. Therefore, FirstEnergy Nuclear Operating Company issued a condition report to document and address this discrepancy.
Design document reviews identified fuel pool purification pump suction piping that penetrates the spent fuel storage pool wall in the cask area and fuel storage area of the pool and extends vertically down to a minimum elevation of 750 feet, 10 inches. Figure 1 shows design feature elevations in a simplified drawing of the spent fuel storage pool. The elevations and dimensions discussed in this evaluation and shown in the figure are nominal values. Technical Specification Section 4.0, "Design Features," Subsection 4.3, "Fuel Storage," Specification 4.3.2, "Drainage," states that for Beaver Valley Power Station, Unit No. 2: The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 751 feet-3 inches. The proposed Technical Specification change would revise the specified elevation to read 750 feet-10 inches. Attachment 1 provides Technical Specification page 4.0-4 marked to show the proposed change. Attachment 2 provides retyped Technical Specification page 4.0-4 incorporating the proposed change. Beaver Valley Power Station, Unit No. 2 Updated Final Safety Analysis Report (UFSAR) Table 1.8-1, "USNRC Regulatory Guides," states that the design of the spent fuel storage facilities follow the guidance of USNRC Regulatory Guide 1.13, "Spent Fuel Storage Facility Design Basis," Revision 1, (Accession No. ML003739943), with certain alternatives.
BVPS-2 UFSAR Section 9.1.2.3, "Safety Evaluation," states in part that:
Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 3 of 9 In accordance with Regulatory Guide 1.13, the storage and handling of fuel in the fuel building is designed to protect the fuel, limit potential offsite exposures, and prevent loss of water from the [spent] fuel [storage]
pool which may uncover the fuel. The spent fuel [storage]
pool is designed such that the water level in the pool cannot be decreased below the top of the fuel stored in the spent fuel racks. The fuel transfer gates do not extend below the top of the spent fuel assemblies, and all piping and piping penetrations of the spent fuel [storage]
pool terminate no lower than 10 feet above the top of the fuel stored in the racks. This UFSAR reference to "the fuel stored in the racks" refers to the top of the active fuel stored in the racks, since the current Technical Specification value of 751 feet, 3 inches is more than 10 feet above the top of the fuel pellets stored in the racks but less than 10 feet above the top of the fuel assemblies.
Section 9.1.3.3, "Safety Evaluation," of the BVPS-2 UFSAR, states in part that: Water level in the spent fuel [storage]
pool cannot be lowered below 10 feet above the top of the fuel stored in the spent fuel racks due to the design of the pool, as described in Section 9.1.2, and by the design of the piping, which does not allow any piping termination below this elevation.
While investigating whether a minimum of 10 feet of water coverage is provided above the top of the fuel stored in the spent fuel storage pool racks, it was discovered that certain racks are higher than expected due to shimming, and the active nuclear fuel pellet stack in the spent fuel assemblies can grow due to irradiation.
The rack shims and the fuel pellet growth can reduce the minimum water coverage over the fuel in the spent fuel storage pool by approximately
0.7 inches
and 1.24 inches, respectively.
FirstEnergy Nuclear Operating Company issued condition reports to document and address these items. The minimum water level over the active fuel when drained to the proposed Technical Specification minimum inadvertent drain level of 750 feet -10 inches, considering the reductions due to rack shims and fuel pellet growth is approximately 9.89 feet. 3.0 TECHNICAL EVALUATION General Design Criterion 61, "Fuel storage and handling and radioactivity control," set forth in Appendix A, "General Design Criteria for Nuclear Power Plants," of 10 CFR 50, requires that fuel storage and handling, radioactive waste, and other systems that may contain radioactivity be designed to assure adequate safety under normal and postulated accident conditions.
The five design provisions listed in General Design Criterion 61 for these systems are presented below. The text that follows each design provision indicates if the design provision relates directly to the proposed Technical Specification change, and if it does not relate, it describes why it does not relate.
Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 4 of 9 These systems shall be designed:
(1) with a capability to permit appropriate periodic inspection and testing of components important to safety, This design provision does not directly relate to the proposed Technical Specification change. The proposed change involves the fuel storage system at BVPS-2 and does not affect fuel handling, radioactive waste, or other systems that may contain radioactivity.
Capability to permit periodic inspection and testing of fuel storage system components (that is, pumps and valves of the spent fuel storage pool cooling and cleanup system) is not affected by the proposed Technical Specification change. (2) with suitable shielding for radiation protection, This design provision directly relates to the proposed Technical Specification change. A discussion of the effects of the proposed Technical Specification change on radiation shielding is provided later in this Technical Evaluation.
(3) with appropriate containment, confinement, and filtering systems, This design provision does not directly relate to the proposed Technical Specification change. The proposed change to the spent fuel storage pool minimum inadvertent drainage elevation does not involve any changes to the containment structure, containment isolation arrangements, the fuel building structure, or the fuel building ventilation system and therefore does not affect the capability to limit the potential release of radioactive iodine and other radioactive materials.
The spent fuel storage pool water level is credited for iodine absorption in the event of a fuel handling accident.
However, inadvertent draining of the spent fuel storage pool to the minimum inadvertent drainage elevation is not postulated to occur coincident with a fuel handling accident.
Twenty-three feet of water in the spent fuel storage pool is assumed for the fuel handling accident.
(4) with a residual heat removal capability having reliability and testability that reflects the importance to safety of decay heat and other residual heat removal, and This design provision does not directly relate to the proposed Technical Specification change. Reducing the spent fuel storage pool minimum inadvertent drainage elevation by five inches does not affect the reliability or testability of spent fuel storage pool residual heat removal capability (that is, the spent fuel storage pool cooling system). However, if the spent fuel storage pool water level was allowed to drop to the proposed minimum inadvertent drainage elevation, the spent fuel pool cooling system will no longer be capable of residual heat removal.
Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 5 of 9 (5) to prevent significant reduction in fuel storage coolant inventory under accident conditions.
This design provision does not directly relate to the proposed Technical Specification change. Accidents related to the spent fuel storage pool are discussed in UFSAR Sections 15.7.4, "Radiological Consequence of Fuel Handling Accidents," and 15.7.5, "Spent Fuel Cask Drop Accidents." Evaluations of these accidents are not affected by the proposed Technical Specification change, because maloperation or passive piping failure causing inadvertent draining of the spent fuel storage pool is not postulated concurrent with the fuel handling or spent fuel cask drop accidents.
The spent fuel storage area is designed in accordance with General Design Criterion 2 as it relates to the facility being capable of withstanding the effects of natural phenomena, such as earthquakes, tornadoes, hurricanes, and floods. The proposed Technical Specification change does not affect the design features of the fuel storage area or fuel building that are provided to withstand the effects of natural phenomenon and therefore, does not affect the capability to withstand the effects of natural phenomenon.
Therefore, the proposed Technical Specification change does not affect design provisions that prevent significant reduction in fuel storage coolant inventory under accident conditions.
Suitable shielding for radiation protection is the only provision of General Design Criterion 61 that relates directly to the proposed Technical Specification change. If the spent fuel storage pool water level was inadvertently reduced through maloperation or piping failure, the water level could drain to the 750 feet, 10 inch elevation.
Although the Technical Specification stated minimum inadvertent drainage elevation needs to be revised to reflect the spent fuel storage pool design, the reduced minimum elevation of piping and penetrations continues to ensure approximately 3 meters (9.84 feet) of water will remain above the top of the active fuel stored in the spent fuel storage pool racks. Three meters of water coverage was selected for evaluation because it bounds the minimum water level of approximately 9.89 feet over the top of the active fuel that is present when the spent fuel storage pool is drained to 750 feet-10 inches. The conservatively high calculated gamma radiation dose rate for personnel located at the fuel building operating floor elevation, directly above freshly discharged fuel assemblies stored in the spent fuel storage pool with the pool water level reduced to the 750 feet, 10 inch elevation (providing at least 9.84 feet of water above the active fuel) is estimated to be approximately 280 millirem per hour. This calculation result can be used to estimate operator exposure for post drain-down event mitigation activities.
The calculated dose rate is comparable to dose rates for certain outage maintenance activities (fall 2012 outage maximum under head inspection dose rate at 185 millirem per hour and maximum steam generator channel head work dose rate at 853 millirem per hour) and permits corrective maintenance to be performed within occupational dose Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 6 of 9 limits of 10 CFR 20.1201. Therefore, it is concluded that the spent fuel storage pool water elevation of 750 feet, 10 inches provides suitable shielding for radiation protection as required by General Design Criterion
- 61. Reducing the spent fuel storage pool minimum shielding depth from the UFSAR specified 10 feet above the top of the fuel stored in the racks to 9.84 feet above the top of the active fuel stored in the racks corresponds to an approximate 51 millirem per hour increase in the radiation dose rate for personnel located at the fuel building operating floor elevation.
As stated above, the calculated dose rate (with this increase) is comparable to dose rates for certain outage maintenance activities and permits corrective maintenance to be performed within occupational dose limits. In summary, this Technical Specification change is being proposed to reflect the actual plant design and the resulting reduction in the available spent fuel storage pool minimum inadvertent drainage elevation.
This reduced minimum water level continues to ensure that in the event of maloperation or failure of the piping, the loss of coolant will not uncover fuel and the remaining water in the spent fuel storage pool will provide adequate shielding for radiation protection.
The proposed Technical Specification change is less restrictive but affords adequate assurance of safety. No design basis accidents are affected by the proposed Technical Specification change.
4.0 REGULATORY EVALUATION
FirstEnergy Nuclear Operating Company proposes to amend Section 4.3, "Fuel Storage," Specification 4.3.2, "Drainage," in the design features section of the Beaver Valley Power Station, Unit No. 2, Technical Specifications.
Specification
4.3.2 identifies
the elevation below which the spent fuel storage pool is designed to prevent inadvertent draining.
The proposed amendment would reduce this minimum specified elevation by 5 inches based on plant design drawings.
4.1 Significant
Hazards Consideration FirstEnergy Nuclear Operating Company has evaluated whether or not a significant hazards consideration is involved with the proposed license amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No. Previously evaluated accidents including a fuel handling accident and spent fuel cask drop accident are not affected by the proposed amendment.
Reducing the minimum water level above fuel stored in the spent fuel storage pool in the event of inadvertent draining as proposed would not involve a significant increase in the probability of a previously evaluated Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 7 of 9 accident.
Maloperation or passive piping failure causing inadvertent draining of the spent fuel storage pool is not postulated concurrent with the fuel handling or spent fuel cask drop accident.
The proposed amendment would not result in any failure modes that could initiate an analyzed accident, and does not increase the likelihood of a malfunction of a system, structure or component; therefore, the probability of analyzed accidents is not affected.
There are no changes to how the station will be operated, limiting conditions for operation, or limiting safety system settings.
The proposed amendment does not affect the capability of a system, structure or component to perform a design function.
Since design functions are not affected by the proposed amendment, the consequences of previously evaluated accidents are not affected.
Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No. Reducing the minimum water level above fuel stored in the spent fuel storage pool in the event of inadvertent draining as proposed does not create any new failure mechanisms, malfunctions, or accident initiators and does not change design functions or system operation in a way that affects the ability of systems, structures, and components to perform design functions.
Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response:
No. General Design Criterion 61, "Fuel storage and handling and radioactivity control," of 10 CFR 50, Appendix A, states in part that fuel storage and handling systems shall be designed with suitable shielding for radiation protection.
The proposed change involves a reduction in the minimum elevation of piping and penetrations of the spent fuel storage pool specified in the Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 8 of 9 Technical Specifications.
In the event maloperation or passive piping failure causes inadvertent draining of the spent fuel storage pool, the remaining water level in the pool ensures the stored fuel remains covered, provides adequate shielding for personnel, and affords adequate assurance of safety when judged against the current regulatory standard of General Design Criterion
- 61. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety. Based on the above, FirstEnergy Nuclear Operating Company concludes that the proposed amendment does not involve a 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.
4.2 Applicable
Regulatory Requirements/Criteria The proposed amendment will continue to ensure compliance with General Design Criterion
- 61. The proposed amendment permits a reduction in the minimum water level above fuel stored in the spent fuel storage pool in the event of inadvertent draining of the pool due to maloperation or a pipe break but still affords adequate assurance of safety by continuing to provide suitable shielding for radiation protection as required by General Design Criterion
- 61. 4.3 Conclusion 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 Commission'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. 5.0 ENVIRONMENTAL CONSIDERATION The proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement.
However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in 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, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
Evaluation of the Proposed Amendment Beaver Valley Power Station, Unit No. 2 Page 9 of 9 ,, ,, l) Top View c:: Pool Area Cask Area tt . -I Transfer Canal I I Side View 2 o__g) Q) '------______,;
I-- I I I I I I I I I I I I I i I i I I I I I I i I I I I I I Spent Fuel I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I No t to Scale I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I <D Elevation of internal bottom of spent fuel storage pool cooling pumps suction pipe where it penetrates the wall of the fuel pool is 750 feet, 10 inches (750.83 feet). <V Elevation at the bottom of the fuel pool purification pumps suction pipes in the pool and cask areas is 750 feet, 10 inches. Elevation at the bottom of the gate opening between the pool area and cask area is 742 feet, 1 inch (742.08 feet). Elevation at the top of the fuel assemblies (not including the top nozzle springs) is 7 41.82 feet. Elevation at the top of the active fuel is 740.94 feet or lower. Figure 1, Spent Fuel Storage Pool 750.83 feet -740.94 feet 9.89 feet Attachment 1 Proposed Technical Specification Change (Mark-Up)
(1 page follows)
4.0 DESIGN
FEATURES 4.3 Fuel Storage (continued)
4.3.2 Drainage
Unit 1 Design Features 4.0 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 750 feet -10 inches. Unit 2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 751 feet 3 inches. 4.3.3 capacity L--------------------'
Unit 1 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1627 fuel assemblies.
Unit 2 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1088 fuel assemblies (Boraflex racks), 1690 fuel assemblies (Metamic racks). Beaver Valley Units 1 and 2 4.0-4 Amendments 278 I 173 Attachment 2 Retyped Technical Specification Page (1 page follows)
4.0 DESIGN
FEATURES 4.3 Fuel Storage (continued)
4.3.2 Drainage
Unit 1 Design Features 4.0 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 750 feet -10 inches. Unit 2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 750 feet-10 inches. 4.3.3 Capacity Unit 1 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1627 fuel assemblies.
Unit 2 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1088 fuel assemblies (Boraflex racks), 1690 fuel assemblies (Metamic racks). Beaver Valley Units 1 and 2 4.0-4 Amendments 278 I TBD