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Category:Letter type:L
MONTHYEARL-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-158, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models L-24-157, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-114, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation L-24-115, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 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-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 272023-11-29029 November 2023 Submittal of the Updated Final Safety Analysis Report, Revision 27 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 2024-09-17
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions 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 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 2024-09-17
[Table view] Category:Technical Specifications
MONTHYEARL-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References ML23198A3592023-10-0202 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) ML21334A0302021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves 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 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 ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications ML20160A0742020-05-20020 May 2020 2 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases 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) 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 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 ML15294A4392015-12-16016 December 2015 Issuance of Amendments License Amendment Request to Revise Steam Generator Technical Specifications (CAC Nos. MF6054 and 6055) 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-14-300, 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 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 L-11-269, Technical Specification 5.6.6.2.1 - Steam Generator Inspection Report2011-09-20020 September 2011 Technical Specification 5.6.6.2.1 - Steam Generator Inspection Report ML1119401232011-07-28028 July 2011 License Amendment, Issuance of Amendment Regarding Approval of the First Energy Nuclear Operating Company Cyber Security Plan 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 ML1108001222011-03-18018 March 2011 Supplement to Spent Fuel Pool Rerack Amendment Request L-11-103, Supplement to Spent Fuel Pool Rerack Amendment Request2011-03-18018 March 2011 Supplement to Spent Fuel Pool Rerack Amendment Request ML1103501622011-02-24024 February 2011 License Amendment, Issuance of Amendment Regarding the Revised Steam Generator Inspection Scope Using F* Inspection Methodology 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 ML0929503052009-11-0505 November 2009 Technical Specifications, Appendices a, B, and C ML0527202912009-11-0505 November 2009 Current Facility Operating License No. DPR-66, Technical Specifications, Revised 03/02/2018 ML0929200562009-11-0505 November 2009 Renewed Facility Operating License, Appendices a, B, and D L-09-025, ISFSI, and Perry, 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 26.2009-03-25025 March 2009 ISFSI, and Perry, 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. L-08-236, License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System2008-09-24024 September 2008 License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System ML0807300272008-03-11011 March 2008 Technical Specifications to Amend 164 ML0805103742008-02-15015 February 2008 Tech Spec Pages for Amendments 281 and 163 Control Room Envelope Habitibility in Accordance with Technical Specification Task Force Traveler 448 ML0728200762007-10-0505 October 2007 Technical Specifications, Issuance of Amendment Changes to the Recirculation Spray System Pump Start Signal Due to the Containment Sump Screen Modification L-07-074, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008)2007-08-30030 August 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008) ML0717202522007-06-14014 June 2007 Beaver and Perry, Technical Specifications, Issuance of Amendments Modification of Technical Specification Requirements for Inoperable Snubbers ML0703902842007-02-21021 February 2007 Improved Technical Specifications L-07-017, License Amendment Requests Nos. 334 and 2052007-02-0909 February 2007 License Amendment Requests Nos. 334 and 205 L-07-006, Technical Specification 6.9.7 - Steam Generator Inspection Report2007-02-0202 February 2007 Technical Specification 6.9.7 - Steam Generator Inspection Report L-06-172, Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2007-01-11011 January 2007 Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process 2024-09-17
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Beaver Valley Power Station Route 168 P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L. William Pearce 724-682-5234 Site Vice President Fax: 724-643-8069 June 2, 2004 L-04-077 U. S . Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 License Amendment Request Nos. 309 and 181 Pursuant to 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) hereby requests an amendment to the above licenses in the form of changes to Technical Specification 3/4 .3 .1, "Reactor Trip System Instrumentation" and 3/4.3 .2, "Engineered Safety Feature Actuation System Instrumentation." Specifically the proposed changes will increase the surveillance test interval from monthly to quarterly for certain reactor trip system and engineered safety feature actuation system channel functional tests. The proposed changes are based on the methodology described in WCAP-10271, "Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and supplements thereto.
The FENOC evaluation of the proposed changes are presented in the Enclosure . The proposed Technical Specification changes are presented in Attachments A-1 and A-2 for BVPS Unit Nos . 1 and 2, respectively . There are no new regulatory commitments made in this letter.
The Beaver Valley Power Station review committees have reviewed the changes. The changes were determined to be safe and do not involve a significant hazard consideration as defined in 10 CFR 50.92 based on the attached safety analysis and no significant hazard evaluation .
FENOC requests approval of the proposed amendment by March 2005 . Once approved, the amendment shall be implemented within 60 days .
If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Performance Improvement at 724-682-5284 .
Beaver Valley Power Station, Unit No. 1 and No. 2 License Amendment Request Nos . 309 and 181 L-04-077 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on June °2. , 2004.
Sincerely,
Enclosure:
FENOC Evaluation ofthe Proposed Changes Attachments:
A-1 Proposed BVPS Unit No . 1 Technical Specification Changes A-2 Proposed BVPS Unit No. 2 Technical Specification Changes c: Mr. T . G . Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
ENCLOSURE FENOC Evaluation of the Proposed Changes Beaver Valley Power Station License Amendment Requests 309 (Unit 1) And 181 (Unit 2)
Subject:
Extension of Selected RTS and ESFAS Surveillance Intervals Table of Contents Section Title Page
1.0 DESCRIPTION
.......................................................................... 1
2.0 PROPOSED CHANGE
S ........................................................... 2
3.0 BACKGROUND
........................................................................ 3
4.0 TECHNICAL ANALYSIS
........................................................ 4 5.0 REGULATORY SAFETY ANALYSIS.................................... 8 5.1 No Significant Hazards Consideration....................................... 8 5.2 Applicable Regulatory Requirements/Criteria......................... 10
6.0 ENVIRONMENTAL CONSIDERATION
............................. 11
7.0 REFERENCES
......................................................................... 12 Attachments Number Title A-1 Proposed Unit 1 Technical Specification Changes A-2 Proposed Unit 2 Technical Specification Changes i
Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
1.0 DESCRIPTION
This is a request to amend Operating Licenses DPR-66 (Beaver Valley Power Station Unit 1) and NPF-73 (Beaver Valley Power Station Unit 2).
The proposed changes will revise the Technical Specifications to permit an increase in surveillance testing intervals (STIs), from monthly to quarterly, for certain reactor trip system (RTS) and engineered safety feature actuation system (ESFAS) channel functional tests in accordance with the methodology presented in the NRC approved WCAP-10271, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System, and supplements thereto.
The specific affected Technical Specification surveillances are:
Unit 1 TS 3/4.3.1, Reactor Trip System Instrumentation, Table 4.3-1 Functional Unit 16- Undervoltage- Reactor Coolant Pumps Functional Unit 17- Underfrequency- Reactor Coolant Pumps TS 3/4.3.2, Engineered Safety Feature Actuation Sys. Instrumentation, Table 4.3-2 Functional Unit 1.1.c- Refueling Water Storage Tank (RWST) Level -Low Functional Unit 6.a- 4.16kv Emergency Bus Undervoltage (Loss of Voltage)
Trip Feed and Start Diesel Functional Unit 6.b- 4.16kv and 480v Emergency Bus Undervoltage (Degraded Voltage)
Functional Unit 7.b- Undervoltage -Reactor Coolant Pump Page 1
Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
Unit 2 TS 3/4.3.1, Reactor Trip System Instrumentation, Table 4.3-1 Functional Unit 16- Undervoltage -Reactor Coolant Pumps (Above P-7)
Functional Unit 17- Underfrequency -Reactor Coolant Pumps (Above P-7)
TS 3/4.3.2, Engineered Safety Feature Actuation Sys. Instrumentation, Table 4.3-2 Functional Unit 1.1.b- RWST Level- Extreme Low Functional Unit 6.a.1- 4.16kv Emergency Bus Undervoltage (Trip Feed)
Functional Unit 6.a.2- 4.16kv Emergency Bus Undervoltage (Start Diesel)
Functional Unit 6.b- 4.16kv Emergency Bus (Degraded Voltage)
Functional Unit 6.c- 480v Emergency Bus (Degraded Voltage)
Functional Unit 7.c- Undervoltage- Reactor Coolant Pump (Start Turbine Driven Pump)
2.0 PROPOSED CHANGE
S The proposed Technical Specification changes, which are submitted for NRC review and approval, are provided in Attachments A-1 and A-2 for Unit Nos. 1 and 2 respectively.
The proposed changes to the Technical Specifications have been prepared electronically. Deletions are shown with a strike-through and insertions are shown double-underlined. This presentation allows the reviewer to readily identify the information that has been deleted and added.
To meet format requirements the Technical Specifications pages will be revised and repaginated as necessary to reflect the changes being proposed by this License Amendment Request (LAR).
The following provides a description of the proposed changes and a basis for the changes.
Change The changes increase the Technical Specification surveillance interval channel functional tests from once per month to once per quarter for the surveillances listed in Section 1.
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Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
Basis for Change The proposed changes are consistent with the Topical Report WCAP-10271 safety evaluation report (SER) conditions, as described below, and reflect the application of methodologies recognized by the NRC and the industry as providing a sufficient margin of safety. Therefore, the proposed changes are considered to be safe and will not reduce the safety of the plant. The reduction in surveillance testing due to the proposed changes provides the following benefits: a reduction in the number of unnecessary plant transients and challenges to the protection systems, a reduction in the amount of time the safety instrumentation is partially operable, more effective use of the operating staff, and a reduction in distractions to the control room operators during testing.
3.0 BACKGROUND
In February 1985, the NRC issued the approving SER for WCAP-10271 and Supplement 1. This SER approved extending the surveillance testing frequency from monthly to quarterly for selected analog channels of the RTS.
In February 1989, the NRC issued the SER for WCAP-10271 Supplement 2 and Supplement 2, Revision 1. This SER approved quarterly testing for selected analog channels of the ESFAS. The ESFAS functions approved are those included in the Westinghouse Standard Technical Specifications (STS).
In April 30, 1990, the NRC issued a Supplemental SER (SSER) for WCAP-10271, Supplement 2 and Supplement 2, Revision 1. The SSER approved quarterly testing for selected analog channels for ESFAS functions not contained in the STS.
The NRC approved extending a number of the Beaver Valley Power Station (BVPS) RTS and ESFAS instrumentation surveillances from monthly to quarterly in 1994 (License Amendment 181 for BVPS Unit 1 and License Amendment 61 for BVPS Unit 2) based on application of the WCAP-10271 program. However, the WCAP- 10271 program did not address all of the RTS and ESFAS channel functional tests specific to each Westinghouse plant. The NRC permits application of the generic WCAP-10271 program methodology to other site specific instrumentation provided that specific conditions contained in the approving SERs and SSER are met. The FirstEnergy Nuclear Operating Company (FENOC) has performed analyses of the applicability of the WCAP-10271 SER and SSER conditions to the additional changes proposed by this LAR.
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Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
4.0 TECHNICAL ANALYSIS
SER Conditions:
The NRC initially imposed five conditions on utilities seeking to implement the Technical Specification changes approved generically for RTS surveillance extensions as a result of their review of WCAP-10271 and WCAP-10271 Supplement 1. Two of the original conditions (i.e. staggered test plan and channels that input to both the RTS and ESFAS) no longer apply. The requirement for a staggered test plan was determined to be unnecessary by the NRC and the condition was removed in the SER dated February 1989 which approved WCAP-10271 Supplement 2 and Supplement 2, Revision 1. This SER, which addressed ESFAS functions, also eliminated concerns related to channels that input to both the RTS and ESFAS. The remaining three conditions applicable to RTS surveillance extensions are identification of common cause failures, installed hardware capability for bypass testing, and setpoint drift. The NRC imposed one additional condition on utilities extending ESFAS surveillances as a result of their review of WCAP-10271 Supplement 2 and Supplement 2, Revision 1. This condition was that the utilities confirm the applicability of the generic analysis to the plant.
SER Condition- Identification of Common Cause Failures This condition requires that plant procedures require a common cause evaluation for failure in the RTS channels changed to the quarterly test frequency and additional testing for plausible common cause failures. In accordance with the Westinghouse Owners Group (WOG) guidance, this condition is also applied to the ESFAS functions.
Response- BVPS maintenance procedures address common cause failure and additional testing of RTS and ESFAS channels.
SER Condition- Installed Hardware Capability for Testing in the Bypass Mode This condition requires that testing of RTS channels in a bypassed condition be performed without the use of temporary jumpers or by lifting leads. In accordance with WOG guidance, this condition is also applied to the ESFAS functions.
Response- BVPS testing procedures do not require the use of temporary jumpers (other than the routine connection of test equipment) or lifted leads for instrument channels that are tested in bypass.
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Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
SER Condition- Setpoint Drift This condition requires that the instrument drift methodology include sufficient adjustments to offset the drift anticipated as a result of less frequent surveillance.
Response
Undervoltage and Underfrequency RTS Relays/Undervoltage and Degraded Voltage ESFAS Relays (Unit 1-Table 4.3-1 Functional Units 16, 17, Table 4.3-2 Functional Units 6.a, 6.b, 7.b; Unit 2-Table 4.3-1 Functional Units 16, 17,Table 4.3-2 Functional Units 6.a.1, 6.a.2, 6.b, 6.c, 7.c)
A study was performed in the year 2000 to evaluate drift for these relays using data from past calibrations and surveillances. The evaluation was performed at a 95%
confidence level. The study concluded that any additional drift experienced as a result of the extended surveillance is adequately accounted for in the instrument setpoint calculations.
Unit 1 RWST Level Low (Table 4.3-2 Functional Unit 1.1.c)
The instrument modules for these channels were replaced in the year 2003 with upgraded modules from an alternate vendor; therefore, limited plant specific historical data exists for these instruments. However, the vendor performed a study of internal drift data measured over a 36-month period. The study, completed in 2001, concluded within a 95% confidence level that setpoint drift would remain within the vendor specification for these instruments. The vendor specification envelops the BVPS drift requirement for these instruments.
Unit 2 RWST Level- Extreme Low (Table 4.3-2 Functional Unit 1.1.b)
In 1993 drift data from surveillances performed in the year 1992 was analyzed for instruments of the same design in similar applications as part of the original submittal for extending surveillance test intervals (License Amendment 181 for BVPS Unit 1 and License Amendment 61 for BVPS Unit 2). The original analysis concluded, within a 95% confidence level, that there would not be any significant increase in out-of- tolerance conditions due to drift. The study found that less than 1.0% of the surveillances had setpoints outside of the established tolerance and required recalibration. In support of this LAR, the BVPS Corrective Action Program was used to search for out-of-tolerance conditions for instruments of the same design with STIs that had been increased from monthly to quarterly. The Page 5
Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2) search period was approximately 2-1/2 years (2001-2003). Consistent with the original analysis in 1993 less than 1% of these instruments had out-of-tolerance-conditions that required recalibration. Based on the original analysis and the recent review it is concluded that extension of the STIs to quarterly intervals will not result in any significant out-of-tolerance conditions due to drift.
SER Condition- Applicability of the Generic Analysis to the Plant This condition requires that the plant specific applications must confirm the applicability of the generic analysis to the plant.
Response- The WCAP methodology addresses two-loop, three-loop, and four-loop Westinghouse plants with relay or solid state systems. WCAP-10271 and supplements addressed changes to the STIs for TS 3/4.3.1 Functional Unit 16 and 17 (Undervoltage/Underfrequency RCPs) at both units and for TS 3/4.3.2 Functional Unit 7.b (Undervoltage- RCP) for Unit 1 and TS 3/4.3.2 Functional Unit 7.c (Undervoltage RCP) for Unit 2.
The remaining changes have been analyzed by Westinghouse using the methodology employed by the WCAP.
The RWST Level channels (Unit 1 -TS 3/4.3.2 Functional Unit 1.1.c; Unit 2- TS 3/4.3.2 Functional Unit 1.1.b) were evaluated by comparing the BVPS signal logic and components with those of a similar case analyzed in WCAP-10271.
The Emergency Bus Undervoltage and Degraded Voltage channels (Unit 1-Functional Unit 6.a, 6.b; Unit 2- Functional Unit 6.a.1, 6.a.2, 6.b, 6.c) were evaluated by individual fault tree analysis.
The evaluations determined that the WCAP-10271 changes, based on a plant specific evaluation, are applicable to the following BVPS signals: Unit 1 TS 3/4.3.2 Functional Unit 1.1.c (RWST Level Low), Functional Unit 6.a (4.16kv Emergency Bus Undervoltage-Loss of Voltage), Functional Unit 6.b (4.16kv and 480v Emergency Bus Undervoltage-Degraded), and Unit 2 TS 3/4.3.2 Functional Unit 1.1.b (RWST Level- Extreme Low), Functional Unit 6.a.1 /6.a.2 (4.16kv Emergency Bus Undervoltage-Loss of Voltage), Functional Unit 6.b (4.16kv Emergency Bus Undervoltage-Degraded), and Functional Unit 6.c (480v Emergency Bus Undervoltage-Degraded). The evaluation concluded that the Page 6
Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2) increase in signal unavailability is very small and that the proposed changes to the STIs are acceptable.
Based on the above considerations, the proposed changes are consistent with the SER(s) conditions and reflect the application of methodologies recognized by the NRC and the industry as providing a sufficient margin of safety. Therefore, the proposed changes are considered to be safe and will not reduce the safety of the plant.
Page 7
Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2) 5.0 REGULATORY SAFETY ANALYSIS The proposed changes will revise the Operating Licenses to permit an increase in surveillance testing intervals (STIs), from monthly to quarterly, for certain reactor trip system (RTS) and engineered safety feature actuation system (ESFAS) channel functional tests in accordance with the methodology presented in the NRC approved WCAP-10271, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System, and supplements thereto.
5.1 No Significant Hazards Consideration FirstEnergy Nuclear Operating Company (FENOC) has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 10 CFR 50.92, Issuance of amendment, as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
Operation of the Beaver Valley Power Station in accordance with the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change modifies surveillance frequencies. Increases in the surveillance test intervals have been established based on achieving acceptable levels of equipment reliability. Consequently, equipment that is required to operate to mitigate an accident will continue to operate as expected and the probability of the initiation of any accident previously evaluated will not be significantly increased. Implementation of the proposed changes does not alter the manner in which protection is afforded.
This equipment will continue to be tested in a manner and at a frequency to give confidence that the equipment can perform its assumed safety function.
As a result, the proposed surveillance requirement changes do not significantly affect the consequences of any accident previously evaluated.
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Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not involve any physical changes to the plant or the modes of plant operation defined in the Technical Specifications. The proposed change does not involve the addition or modification of plant equipment nor does it alter the design or operation of any plant systems. No new accident scenarios, transient precursors or failure mechanisms are introduced as a result of these changes.
There are no changes in this proposal that would cause the malfunction of safety-related equipment assumed to be operable in accident analyses. No new mode of failure has been created and no new equipment performance requirements are imposed. The proposed change has no effect on any previously evaluated accident.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The change in surveillance frequencies has been evaluated to ensure that it provides an acceptable level of equipment reliability. Equipment continues to be tested at a frequency that gives confidence that the equipment can perform its assumed safety function when required. The proposed changes do not alter the manner in which safety limits, limiting safety system setpoints or limiting conditions for operations are determined. The impact of reduced testing is to allow a longer time interval over which instrument uncertainties (e.g. drift) may act. Experience has shown that the initial uncertainty assumptions are valid for reduced testing.
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Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
Implementation of the proposed changes is expected to result in an overall improvement in safety since plant transients initiated from inadvertent safety system actuation should be reduced. Less frequent testing will reduce the likelihood for inadvertent reactor trips and inadvertent actuation of Engineered Safety Features Actuation System components.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, FENOC concludes that the proposed amendments present no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.
5.2 Applicable Regulatory Requirements/Criteria In the following paragraphs applicable criteria as they are related to the proposed changes are discussed. A summary of the applicable criteria and assessment of the impact to the BVPS design conformance are provided in the following table.
General Design Criteria Impact 1 Quality Standards and Records None 2 Design Bases for Protection against Natural None Phenomena.
4 Environmental and Dynamic Effects Design Bases None 10 Reactor Design None 13 Instrumentation and Control None 15 Reactor Coolant System Design None 17 Electric Power Systems None 18 Inspection and Testing of Electric Power Systems None 20 Protection System Functions None 21 Protection System Reliability and Testability None Page 10
Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2) 5.2.1 Discussion of Impacts The proposed changes increase surveillance test intervals from monthly to quarterly. Specific surveillance times are not listed in the UFSAR and no change is being made which alters the functioning of the RTS or the ESFAS.
Consequently, the proposed changes do not impact the design or performance characteristics of the RTS or ESFAS.
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 Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 ENVIRONMENTAL CONSIDERATION
A review has determined that 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 effluent 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.
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Beaver Valley Power Station License Amendment Requests 309 (Unit 1) and 181 (Unit 2)
7.0 REFERENCES
- 1. 10 CFR 50, Appendix A, General Design Criteria for Nuclear Power Plants.
- 2. WCAP-10271, Supplement 1-P-A, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System
- 3. WCAP-10271, Supplement 1-P-A, Supplement 2, Revision 1, Evaluation of Surveillance Frequencies and Out of Service Times for the Engineered Safety Features Actuation System
- 4. TOP (Technical Specification Optimization Program) Guidelines- August 1990 (Final) WOG Guidelines for Preparing Submittals Requesting Revision of RPS Technical Specifications based on Generic Approval of WCAP-10271 and Supplements
- 5. Westinghouse Letter, dated July 10, 2003 Transmittal of WCAP-10271 Evaluations for BVPS 1 and 2 Safety Injection- Transfer from Injection to the Recirculation Mode and Loss of Power Signals
- 6. Westinghouse Letter, dated April 21, 2004 RWST Switchover TOP Justification Page 12
Attachment A-1 Beaver Valley Power Station, Unit No. 1 Proposed Technical Specification Changes License Amendment Request No. 309 The following is a list of the affected pages:
3/4 3-12 3/4 3-29a 3/4 3-31 3/4 3-31a
TABLE 4.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Which Channel Channel Functional Surveillance Functional Unit Check Calibration Test Required
- 12. Loss of Flow - Single Loop S R Q 1
- 13. Loss of Flow - Two Loops S R Q 1
- 14. Steam/Generator Water S R Q 1, 2 Level-Low-Low
- 15. DELETED
- 16. Undervoltage-Reactor Coolant N.A. R M Q 1 Pumps
- 17. Underfrequency-Reactor N.A. R M Q 1 Coolant Pumps
- 18. Turbine Trip
- a. Auto Stop Oil Pressure N.A. N.A. S/U(1) 1, 2
- b. Turbine Stop Valve N.A. N.A. S/U(1) 1, 2 Closure
- 19. Safety Injection Input from N.A. N.A. R 1, 2 ESF
- 20. Reactor Coolant Pump Breaker N.A. N.A. R N.A.
Position Trip
- 21. Reactor Trip Breaker N.A. N.A. M(5,11) 1, 2, 3(14),
and S/U(1) 4(14), 5(14)
BEAVER VALLEY - UNIT 1 3/4 3-12 Amendment No. 240
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE
- a. Manual Initiation N.A. N.A. R 1, 2, 3, 4
- b. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3 Coincident with Safety Injection Signal
- c. Refueling Water Storage S R M Q 1, 2, 3 Tank Level-Low
- d. Refueling Water Storage S R M 1, 2, 3 Tank Level - Auto QS Flow Reduction
- 2. CONTAINMENT SPRAY
- a. Manual Initiation N.A. N.A. R 1, 2, 3, 4
- b. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3, 4
- c. Containment Pressure- S R Q 1, 2, 3 High-High BEAVER VALLEY - UNIT 1 3/4 3-29a Amendment No. 229
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 4. STEAM LINE ISOLATION
- a. Manual N.A. N.A. R 1, 2, 3
- b. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3
- c. Containment Pressure-- S R Q 1, 2, 3 Intermediate-High-High
- d. Steamline Pressure--Low S R Q 1, 2, 3
- e. Steamline Pressure Rate-High S R Q 1, 2, 3 Negative
- 5. TURBINE TRIP & FEEDWATER ISOLATION
- a. Steam Generator Water Level-- S R Q 1, 2, 3 High-High
- 6. LOSS OF POWER
- a. 4.16kv Emergency Bus Under- N.A. R M Q 1, 2, 3, 4 voltage (Loss of Voltage)
Trip Feed & Start Diesel
- b. 4.16kv and 480v Emergency N.A. R M Q 1, 2, 3, 4 Bus Undervoltage (Degraded Voltage)
BEAVER VALLEY - UNIT 1 3/4 3-31 Amendment No. 239
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 7. AUXILIARY FEEDWATER
- a. Steam Generator Water S R Q 1, 2, 3 Level-Low-Low
- b. Undervoltage-RCP S R M Q 1, 2
- c. S.I. See 1 above (all SI surveillance requirements)
- d. (Deleted)
- e. Trip of Main N.A. N.A. R 1, 2, 3 Feedwater Pumps
- 8. ESF INTERLOCKS
- a. P-4 N.A. N.A. R 1, 2, 3
- b. P-11 N.A. R Q 1, 2, 3
- c. P-12 N.A. R Q 1, 2, 3 BEAVER VALLEY - UNIT 1 3/4 3-31a Amendment No. 239
Attachment A-2 Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Bases Changes License Amendment Request No. 181 The following is a list of the affected pages:
3/4 3-11 3/4 3-33 3/4 3-36 3/4 3-37
TABLE 4.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Which Channel Channel Functional Surveillance Functional Unit Check Calibration Test Required
- 12. Loss of Flow - Single Loop S R Q 1 (Above P-8)
- 13. Loss of Flow - Two Loop S R Q 1 (Above P-7 and Below P-8)
- 14. Steam/Generator Water Level- S R Q 1, 2 Low-Low
- 15. DELETED.
- 16. Undervoltage-Reactor Coolant N.A. R M Q 1 Pumps (Above P-7)
- 17. Underfrequency-Reactor N.A. R M Q 1 Coolant Pumps (Above P-7)
- 18. Turbine Trip (Above P-9)
A. Emergency Trip Header N.A. R S/U(1) 1, 2 Low Pressure B. Turbine Stop Valve N.A. R S/U(1) 1, 2 Closure
- 19. Safety Injection Input from N.A. N.A. R 1, 2 ESF
- 20. Reactor Coolant Pump Breaker N.A. N.A. R N.A.
Position Trip (Above P-7)
- 21. Reactor Trip Breaker N.A. N.A. M(5, 11) (1) 1, 2, 3(14)
(14) and S/U 4 , 5(14)
BEAVER VALLEY - UNIT 2 3/4 3-11 Amendment No. 61
TABLE 4.3-2 ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 1. SAFETY INJECTION AND FEEDWATER ISOLATION
- a. Manual Initiation N.A. N.A. R 1, 2, 3, 4
- b. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3, 4 and Actuation Relays
- c. Containment Pressure-High S R Q 1, 2, 3
- d. Pressurizer Pressure--Low S R Q 1, 2, 3
- e. Steam Line Pressure--Low S R Q 1, 2, 3 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE
- a. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3, 4 Coincident with Safety Injection Signal
- b. Refueling Water Storage S R M Q 1, 2, 3, 4 Tank Level-Extreme Low BEAVER VALLEY - UNIT 2 3/4 3-33 Amendment No. 108
TABLE 4.3-2 (Continued)
ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 6. LOSS OF POWER
- a. 4.16kv Emergency Bus
- 1. Undervoltage (Trip Feed) N.A. R M Q 1, 2, 3, 4
- 2. Undervoltage (Start N.A. R M Q 1, 2, 3, 4 Diesel)
- b. 4.16kv Emergency Bus N.A. R M Q 1, 2, 3, 4 (Degraded Voltage)
- c. 480v Emergency Bus N.A. R M Q 1, 2, 3, 4 (Degraded Voltage)
- 7. AUXILIARY FEEDWATER(4)
- a. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3 and Actuation Relays
- b. Steam Generator Water Level-Low-Low
- 1. Start Turbine Driven S R Q 1, 2, 3 Pump
- 2. Start Motor Driven Pumps S R Q 1, 2, 3 (4) Manual initiation is included in Specification 3.7.1.2.
BEAVER VALLEY - UNIT 2 3/4 3-36 Amendment No. 108
TABLE 4.3-2 (Continued)
ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 7. AUXILIARY FEEDWATER (continued)
- c. Undervoltage - RCP (Start S R M Q 1, 2 Turbine-Driven Pump)
- d. Safety Injection (Start All See 1 above (all SI surveillance requirements)
Auxiliary Feedwater Pumps) e Trip of Main Feedwater Pumps N.A. N.A. R 1, 2, 3 (Start Motor-Driven Pumps)
- 8. ENGINEERED SAFETY FEATURE INTERLOCKS
- a. Reactor Trip, P-4 N.A. N.A. R 1, 2, 3
- b. Pressurizer Pressure, P-11 N.A. R Q 1, 2, 3
- c. Low-Low Tavg, P-12 N.A. R Q 1, 2, 3 BEAVER VALLEY - UNIT 2 3/4 3-37 Amendment No. 108