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Category:Letter type:L
MONTHYEARL-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan 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-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023 Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002 L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023 CFR 50.55a Request RP-5 Regarding Inservice Pump Testing L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022 Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS) L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022 Occupational Radiation Exposure Report for Year 2021 - Correction L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022 Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022 Submittal of Evacuation Time Estimates L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022 Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022 Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022 Readiness for NRC Supplemental Inspection Required for a White Finding L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022 Withdrawal of Proposed Inservice Inspection Alternative RR-A2 L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022 Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage L-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022 Report of Facility Changes, Tests, and Experiments L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022 Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021 L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 12022-05-10010 May 2022 Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1 L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding2022-05-0606 May 2022 Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding L-22-089, Occupational Radiation Exposure Report for Year 20212022-04-12012 April 2022 Occupational Radiation Exposure Report for Year 2021 L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022 Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022 Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3 L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-15015 March 2022 Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations L-22-061, Ile Post Exam Letter L-22-0612022-02-24024 February 2022 Ile Post Exam Letter L-22-061 L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022 Retrospective Premium Guarantee L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022 Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 L-20-289, Emergency Plan Amendment Request2022-01-19019 January 2022 Emergency Plan Amendment Request L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-1762021-12-21021 December 2021 Response to NRC Inspection Report 05000346/2021091, EA-21-176 2023-09-12
[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 ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure 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-20-188, 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 L-19-233, License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-11-14014 November 2019 License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition2019-02-27027 February 2019 Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan2019-02-0505 February 2019 License Amendment Request - Proposed Post-Shutdown Emergency Plan L-18-242, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition2019-02-0505 February 2019 License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2018-10-22022 October 2018 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition L-18-203, Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2018-08-23023 August 2018 Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement 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-17-026, Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years2017-01-23023 January 2017 Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016 Supplement to Request for License Amendment Approval Delay L-16-020, Request for Licensing Action to Revise the Emergency Plan2016-02-17017 February 2016 Request for Licensing Action to Revise the Emergency Plan L-16-030, Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program.2016-02-0909 February 2016 Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program. 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-15-309, License Renewal Application Amendment No. 602015-10-0606 October 2015 License Renewal Application Amendment No. 60 L-15-214, License Renewal Application Amendment No. 59 - Annual Update2015-06-29029 June 2015 License Renewal Application Amendment No. 59 - Annual Update L-15-192, Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 582015-06-12012 June 2015 Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 58 L-15-166, Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 562015-05-20020 May 2015 Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 56 L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 552015-04-0808 April 2015 Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55 L-15-117, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2015-04-0101 April 2015 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014 Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program L-14-297, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 532014-09-16016 September 2014 Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 53 L-14-206, License Renewal Application Amendment No. 50 - Annual Update2014-06-23023 June 2014 License Renewal Application Amendment No. 50 - Annual Update L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 482014-02-19019 February 2014 License Renewal Application (TAC No. ME4640) Amendment No. 48 L-13-330, License Renewal Application Amendment No. 46 - Annual Update2013-09-20020 September 2013 License Renewal Application Amendment No. 46 - Annual Update 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-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013 License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6.. ML12229A1392012-08-0909 August 2012 License Renewal Application Amendment 30 - Annual Update L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels2012-05-23023 May 2012 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels ML1126402462011-09-20020 September 2011 License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.2011-05-20020 May 2011 License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program. ML1024505632010-08-31031 August 2010 Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Section 3.5 Through Appendix E, References 2.3-1 L-10-221, Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.112010-08-31031 August 2010 Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.11 L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation.2009-06-0202 June 2009 License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation. L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.2009-04-15015 April 2009 License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr. 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-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD63982008-05-16016 May 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398 ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) ML0814804672008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits ML0814804662008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems 2023-09-12
[Table view] Category:Technical Specifications
MONTHYEARML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements 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 ML20280A8272020-11-0303 November 2020 Issuance of Amendment No. 301 to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML20213C7262020-08-24024 August 2020 Issuance of Amendment No. 300 to Revise the Containment Leakage Rate Testing Program ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 ML16342C9462017-01-12012 January 2017 Issuance of Amendment Revising Emergency Action Level Scheme ML16040A0842016-06-0707 June 2016 FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications ML16083A4812016-04-27027 April 2016 Issuance of Amendment Revising Emergency Diesel Generator Minimum Voltage and Frequency Acceptance Criteria ML15251A0462015-10-20020 October 2015 Issuance of Amendment Revising Containment Spray Nozzle Surveillance Requirement L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014 Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013 License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6.. L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels2012-05-23023 May 2012 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels ML1208604472012-04-18018 April 2012 Issuance of Amendment Modification of the Special Visual Inspection Requirement of TS 5.5.8 Steam Generator Program L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.2011-05-20020 May 2011 License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program. 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. ML0822706662008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 10, Revision 1, ITS Section 3.5, Emergency Core Cooling Systems L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations2008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations ML0822706612008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 1, Revision 1, Application of Selection Criteria to the Dbnps Technical Specifications ML0822706622008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 2, Revision 1, Generic Determination of No Significant Hazards Consideration and Environmental Assessment ML0822706672008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 16, Revision 1, ITS Chapter 5.0, Administrative Controls ML0822706702008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 13, Revision 1, ITS Section 3.8, Electrical Power Systems ML0822706692008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 12, Revision 1, ITS Section 3.7, Plant Systems ML0822706652008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 8, Revision 1, Section 3.3 - Instrumentation ML0822706642008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request, Volume 4, Revision 1, ITS Chapter 2.0, Safety Limits ML0822706632008-08-0707 August 2008 Improved Technical Specification Conversion License Amendment Request Volume 3, Revision 1, ITS Chapter 1.0, Use and Application ML0822706582008-08-0707 August 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications to Improved Technical Specifications - Volumes 1, 2, 3, 4, 8, 10, 12, 13, 14, and 16 ML0818306382008-06-30030 June 2008 Tech Spec Pages for Amendment 278 Regarding Measurement Uncertainty Recapture Power Uprate ML0826005772008-05-30030 May 2008 Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website ML0814804672008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits ML0814804652008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 5, (Revision 1), Section 3.0 - LCO and SR Applicability ML0814804662008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features L-08-065, Response to Request for Additional Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate2008-02-20020 February 2008 Response to Request for Additional Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate ML0729601812007-10-17017 October 2007 Technical Specifications, Issuance of Amendment Administrative Control of Penetrations During Refueling ML0722004632007-08-0303 August 2007 Volume 5, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.0 LCO and SR Applicability. ML0722004512007-08-0303 August 2007 Submittal of License Amendment Request No. 06-0003 to Revise Current Technical Specifications to the Improved Technical Specifications ML0722004862007-08-0303 August 2007 Volume 17, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, Current Technical Specification Markup in CTS Order. ML0722004852007-08-0303 August 2007 Volume 16, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Chapter 5.0 Administrative Controls. ML0722004542007-08-0303 August 2007 Volume 1, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, Application of Selection Criteria. ML0722004562007-08-0303 August 2007 Volume 2, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, Generic Determination of No Significant Hazards Consideration and Environmental Assessment. 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FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 May 23,2012 L-12-070 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 License Amendment Request To Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels FirstEnergy Nuclear Operating Company hereby requests amendment of the operating license for the Davis-Besse Nuclear Power Station. The proposed amendment would revise Technical Specification 3.8.1, "AC Sources - Operating" to change the minimum voltage acceptance criterion for emergency diesel generator surveillance testing in surveillance requirements 3.8.1.8 and 3.8.1.14 from greater than or equal to 4031 volts to greater than or equal to 4070 volts. The proposed amendment would also add axis labels to Technical Specification Figure 3.7.18-1, "Maximum Allowable Steam Generator LeveL" The Enclosure provides a description and evaluation of the proposed amendment, including a copy of the existing Technical Specification pages marked up to reflect the proposed amendment and re-typed Technical Specification pages with the proposed amendment incorporated.
Approval of the proposed license amendment is requested by May 30, 2013, and the amendment would be implemented within 60 days of approval.
There are no regulatory commitments contained in this letter. If there are any questions, or if additional information is required, please contact Mr. Phil H. Lashley, Supervisor - Fleet Licensing, at 330-315-6808.
Davis-Besse Nuclear Power Station L-12-070 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on May ~3 , 2012.
Sincerely B:!s~en
Enclosure:
Evaluation of Proposed Amendment cc: NRC Region III Administrator NRC Project Manager NRC Resident Inspector Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Evaluationof the ProposedAmendment Page 1 ot7
Subject:
LicenseAmendmentRequestto Revisethe EmergencyDieselGenerator MinimumVoltageSurveillance Requirements,and Add FigureAxis Labels Tableof Contents 1.0
SUMMARY
D E S C R I P T I O. .N. . . . . . . ......2 2.0 D E T A I L E D E S C R I P T I O. .N. . . . . . . . ,.....2 3.0 T E C H N I C AELV A L U A T I O N ...............3 3 . 1 E v a l u a t i oonf M i n i m u m Voltage Change .....................3 3 . 2 E va l u a ti oonf A xi sL a belAddition ....,..........4 4.0 R E GU L A T OREYV A L U A T ION .,.... .....4 4 . 1 N o S i g n i fi ca nHta za rds Consider ation Analysis............ .......... ......4 4.2 Applicable Regulatory Requirements/Criteria ..............6 4.3 Conclusions.............. .................7 5 . 0 E N V I R O N M E N TC AO L NSIDERATION... ...........,7
6.0 REFERENCES
......... .........7 Attachments A. ProposedTechnicalSpecification Changes B. RetypedTechnicalSpecification Pages
Page2 of 7 1.0
SUMMARY
DESCRIPTION This evaluationsupportsa requestto amendOperatingLicenseNPF-3for the Davis-Besse NuclearPowerStation.The proposedchangewouldreviseTechnical Specification 3.8.1,"AC Sources- Operating" to changethe minimumvoltage acceptancecriterionfor emergencydieselgenerator(EDG)surveillance testingin surveillance requirements 3.8.1.8and 3.8.1.14fromgreaterthanor equalto (>)4031 volts(V) to > 4070V. The proposedchangewouldalsoadd axis labelsto Technical Specification Figure3.7.18-1,"MaximumAllowableSteamGeneratorLevel."
2 . 0 D ET A IL E D D E S C R IP T ION The proposedtechnicalspecification changesare providedin AttachmentA.
AttachmentA showsdeletionswith a strike-through and insertionsunderlined, with a verticallinein the marginshowingthe areaof change. Retypedtechnical specification pagesare providedfor information in AttachmentB.
The followingchangesare proposed:
- 1. Specification 3.8.1,"AC Sources- Operating" The EDGminimumvoltageacceptance specifiedin surveillance criterion r e q u i re me n3ts.8 .1 .8a n d3 .8.1.14willbe changed fr om4031V to 4070V as shownbelow.The specified timeof lessthanor equalto (<) 10 secondsand frequencyof > 58.8 hertz(Hz)are not revised.
Surveillance Requirement 3.8.1.8- Verifyeach EDGstartsfromstandby condition and achieves:
- a. ln < 10 seconds,voltage> 4070V and frequency > 58.8Hz,and Surveillance Requirement 3.8.1.14 -YerifyeachEDGstartsand achieves:
- a. In s 10 seconds,voltage> 4070V and frequency > 58.8Hz,and
- 2. Specification 3.7.18,"SteamGenerator Level" The followingX and Y axislabelswill be addedto TechnicalSpecification Figure 3 . 7 . 1 8 -. 1 X axislabel: STEAMSUPERHEAT fF)
Y axislabel: MAXIMUMALLOWABLE OPERATING LEVET(o/o)
UpdatedSafetyAnalysisReport,Subsection 8.3.1.1.4.1,"Emergency Diesel Generators," states that two redundant EDG units,one connected to essential4160V busC1 and the otherconnected to essential4160 V bus D1,are providedas onsite standbypowersourcesto supplytheirrespectiveessentialbusesuponlossof the normaland reservepowersources.The EDG is capableof attainingratedfrequency and voltageapproximately 10 secondsafterthe enginestartsignalis received.
Surveillance requirements 3.8.1.8.a and 3.8.1.14.a demonstrate thatthe EDGis capableof attainingthe requiredvoltageand frequencywithin10 secondsafterthe enginestartsignalis received.Technicalspecification basesassociated with surveillance requirements 3.8.1.8and 3.8.1.14statethatthe minimumvoltagelimitis
Pa g e3 o f7 basedon the voltagerequiredfor EDG breakerclosureand the minimumfrequencylimit is basedon the recommendations in SafetyGuide9 (Reference1).
Operatingexperienceindicatedthatthe minimumvoltagelimitspecifiedin surveillance requirements 3.8.1.8.a and 3.8.1.14.a may be nonconservative. A subsequent evaluationdemonstrated that this minimumvoltagelimitwas insufficientto ensure automaticclosureof the EDG outputcircuitbreaker.Thesefindingswere documented in FirstEnergy NuclearOperatingCompany'scorrectiveactionprogram.
The linechartshownin TechnicalSpecification Figure3.7.18-1wasrevisedas partof the conversionto the improvedtechnicalspecifications and submittedin Attachment1 of a supplementletterdatedAugust7,2008 (Reference 2). The changeto add axis labelscorrectsthe inadvertent omissionof the labelswhenFigure3.7.18-1was submittedin a letterdatedOctober21,2008 (Reference3) with the finalcopyof the improvedtechnicalspecifications.
3.0 TECHNICALEVALUATION 3.1 Evaluation of MinimumVoltageChange Accidentanalysescreditthe loadingof the EDG,followinga postulatedlossof offsite power,duringa lossof coolantaccident.The actualEDGstarthas historically been associatedwith the safetyfeaturesactuationsystemactuation.The EDG loadinghas beenincludedin the delaytime associated with eachsafetysystemcomponent requiringEDG supplied power followinga lossof offsitepower. This delaytime includes contributions fromthe EDG start,EDG loading,and safetyinjectionsystemcomponent actuation.The responseof the EDGto a lossof powermustbe demonstrated to be withinthisanalysisresponsetimewhenincluding the contributionsof all portions of the delay. The delaytimesassumedin the safetyanalysisfor the ESFequipment include the 10 secondEDGstartdelayand,if applicable, the appropriate sequencing delay.
Surveillance Requirement 3.8.1.8.a demonstrates thatthe EDGcan startfromstandby conditionsand achievethe requiredvoltageand frequencywithin10 seconds.
Surveillance Requirement 3.8.1.14.ademonstrates thatthe dieselenginecan restart from a hot condition,suchas subsequent to shutdownfrom normalsurveillances, and achievethe requiredvoltageand frequencywithin10 seconds.The 10 secondstart requirement supportsthe assumptions of the designbasislossof coolantaccident analysis.The minimumvoltagelimitis basedon the voltagerequiredfor EDG breaker closure,and the minimumfrequencylimitis basedon the recommendations in Safety G u i d e9 .
The proposedchangewill modifythe minimumvoltageacceptancecriteriafor s u r v e i l l a n ce re q u i re me n3ts.8 .1 .8.a and3.8.1.14.a. Theexisting minimum voltage acceptancecriterionof greaterthan or equalto 4031V will be increasedto a more restrictiveminimumvoltageacceptancecriterionof greaterthan or equalto 4070V.
The minimumacceptablevoltageof 4070V was determinedbasedon the bus voltage requiredby the EDG outputcircuitbreakervoltagepermissiverelaycircuitry.This circuitryrequiresthe voltageto be withina rangethat is 95 percentof the voltageon the low voltagesideof the meteringpotentialtransformer(120V), plusor minus2-percent
P a g e4 o l 7 to accountfor the settingtoleranceof the voltagepermissiverelay.The bus voltage rangeis then determinedby increasing the voltageby the transformerratioof 35 to 1, resulting in a rangeof 3910.2Vto 4069.8V.
The existingminimumfrequencyof > 58.8 Hz, requiredby surveillance requirements 3.8.1.8and 3.8.1.14,is acceptable per SafetyGuide9 and doesnot needto be changed.
3.2 Evaluation of Axis LabelAddition The proposedadditionof axislabelsto Technical SpecificationFigure3.7.18-1, "MaximumAllowableSteamGeneratorLevel"is an administrative changeto reflectthe axis labelsproposedduringthe conversionto improvedtechnicalspecifications, but inadvertently omittedwhenthe finaltypedpageswereforwardedto the NRC beforethe amendment was issued.
4,0 REGULATORY EVALUATION FirstEnergy NuclearOperatingCompanyproposesto reviseTechnicalSpecification 3.8.1, "AC Sources- Operating," to changethe minimumvoltageacceptance criterion for emergency dieselgenerator surveillancetestingin surveillancerequirements 3.8.1.8 and 3.8.1.14fromgreaterthanor equalto 4031voltsto greaterthanor equalto 4070 volts. The proposedchangewouldalsoadd axis labelsto TechnicalSpecification Figure3.7.18-1, "Maximum AllowableSteamGenerator Level."
The proposedsurveillance requirement changesaddressa nonconservative minimum voltageacceptancecriteriondiscoveredduringthe reviewof operatingexperience.The revisedsurveillance requirements helpto ensurethe availabilityof the standbyelectrical powersupplyto mitigatedesignbasisaccidentsand transientsand to maintainthe unit in a safeshutdowncondition.
The proposedadditionof axislabelsto Technical SpecificationFigure3.7.18-1, "MaximumAllowableSteamGeneratorLevel,"is an administrative changeto reflectthe axis labelsproposedduringthe conversionto improvedtechnicalspecifications, but inadvertently omittedwhenthe finaltypedpageswere forwardedto the Nuclear RegulatoryCommissionbeforethe amendmentwas issued.
4.1 No SignificantHazardsConsideration Analysis FirstEnergy NuclearOperatingCompanyhas evaluatedwhetheror not a significant hazardsconsideration is involvedwiththe proposedamendmentby focusingon the threestandards set forthin 10 CFR50.92."lssuance of amendment," as discussed below.
L Doesthe proposedamendmentinvolvea significantincreasein the probability or consequences of an accidentpreviouslyevaluated?
Response: No.
The proposedamendmentincreasesthe minimumrequiredemergencydiesel generatoroutputvoltageand addsaxislabelsto Figure3.7.18-1.The increase
P a g e5 o t7 in the minimumemergencydieselgeneratoroutputvoltageacceptance value in TechnicalSpecification 8.3.1surveillance requirements does not adversely affectany of the parametersin the accidentanalyses.The increasein minimumoutputvoltageensuresthat sufficientvoltageis availableto closethe emergencydieselgeneratoroutputbreaker.This conservative changeof the emergencydieselgeneratorvoltageoutputacceptancecriteriadoes not affect the probabilityor consequences of evaluatedaccidents,but ratherprovides assurancethat emergencydieselgeneratorswill providea sufficientvoltage for eventmitigation.The changeto add axislabelsto Figure3.7.18-1is administrative in nature.The proposedamendmentdoes not resultin failure modesthat couldinitiatean accident,or physicalplantmodifications that affect the operationor capabilityof systems,structuresor components to mitigate evaluatedaccidents.
Therefore,the proposedamendmentdoes not involvea significantincreasein the probabilityor consequences of an accidentpreviouslyevaluated.
2 . Doesthe proposedamendmentcreatethe possibilityof a new or differentkind of accidentfrom any accidentpreviouslyevaluated?
Response: No.
The proposedchangedoes not introducea new modeof plantoperationor involvea physicalmodification to the plant.Newequipmentis not installedwith the proposedamendment,nor doesthe proposedamendmentcauseexisting equipmentto be operatedin a new or differentmanner.The changeto add axis labelsto Figure3.7.18-1is administrative in nature.Sincethe proposed amendment doesnot involvea changeto the plantdesignor operation, no newsysteminteractions are createdby this change.The proposedchanges do not resultin any newfailuremodes,and thus cannotinitiatean accident differentfromthosepreviouslyevaluated.
Therefore,the possibilityof a new or differentkindof accidentfrom any previouslyevaluatedhas not beencreated.
3 . Doesthe proposedamendmentinvolvea significantreductionin a marginof safety?
Response: No.
The proposedamendmentdoes not affectemergencydieselgenerator performance as describedin the designbasisanalyses,includingthe capabilityfor the emergencydieselgeneratorto attainand maintainrequired voltageand frequencyfor acceptingand supportingplantsafetyloadsshould an emergencydieselgeneratorstartsignalbe received.The operability of the emergencydieselgeneratorcontinuesto provideemergencypowerto plant equipmentthat mitigatethe consequences of a transientor accident,and maintainsthe emergencydiesel generator's system'scapabilityto respond
Page6 of 7 withinthe timeassumedin the accidentanalyses. The changeto add axis labelsto Figure3.7.18-1is administrative in nature.
The proposedchangedoes not introducea new modeof plantoperationor involvea physicalmodification to the plant. The proposedamendmentdoes not introducechangesto limitsestablished in the accidentanalysis.
Therefore,the proposedamendmentdoes not involvea significantreductionin a marginof safety.
Basedon the above,FirstEnergy NuclearOperatingCompanyconcludesthatthe proposedamendmentdoes not involvea significanthazardsconsideration underthe standards set forthin 10 CFR50.92(c), and,accordingly, a findingof "no significant hazardsconsideration" is justified.
4.2 ApplicableRegulatoryRequirements/Criteria Changesdescribedin the licenseamendmentrequestcomplywith the following regulations; and continueto meetthe intentof the applicable GeneralDesignCriteria.
10 CFR Part50.36,"TechnicalSpecifications," requiresin paragraph50.36(cX2XiiXB)
Criterion2 thata technicalspecification limitingconditionfor operationbe established for a processvariable,designfeature,or operatingrestriction that is an initialcondition of a designbasisaccidentthat eitherassumesthe failureof or presentsa challengeto the integrityof a fissionproductbarrier.The steamgeneratorlevellimitingconditionfor operationsatisfiesCriterion2.
10 CFR Part50.36,"Technical Specifications,"requiresin paragraph 50.36(cX3) that technicalspecifications includesurveillance requirements relatingto test,calibration,or inspection to assurethatthe necessaryqualityof systemsand componentsis maintained, thatfacilityoperationwill be withinsafetylimits,and thatthe limiting conditionsfor operationwill be met.The technicalspecification basesfor limiting conditionfor operation3.8.1statesthat each EDG mustbe capableof starting, accelerating to ratedspeedand voltage,connectingto its respectiveessentialbus on detection of bus undervoltage, andthiswill be accomplished within10 seconds.
Surveillance requirements 3.8.1.8and 3.8.1.14verifythatthe emergency diesel generatorscan startfromstandbyconditionsand restartfrom a hot condition (respectively) and achievethe requiredvoltageand frequencywithin10 seconds.
10 CFR50,AppendixA, GeneralDesignCriterion (GDC)17,"ElectricPowerSystems,"
includesrequirements to ensurean onsiteelectricpowersystemis providedto permit functioningof structures, systems,and componentsimportantto safety.
GDC 18,"lnspection andTestingof ElectricPowerSystems," includesrequirements to ensureelectricpowersystemsimportantto safetyare designedto permitappropriate periodicinspectionand testingof importantareasand features.
Thereis no effecton the emergency dieselgenerator capabilityto supplythe minimum voltageand frequencyrequiredwithinthe time assumedin the safetyanalyses.The applicabletechnicalspecification surveillance will continueto verifythe capabilityof the
P a g e7 o f7 emergencydieselgeneratorto startand accelerateto the requiredspeedand voltage within10 seconds.Maintenance and monitoringof the emergencydieselgeneratorwill be maintained perthe Maintenance Rule(10 CFR50.65,"Requirements for monitoring the effectiveness of maintenance at nuclearpowerplants")and the MitigatingSystem Performance lndicatorProcess.
4.3 Conclusions Basedon the considerations discussedabove,(1) thereis reasonableassurancethat the healthand safetyof the publicwill not be endangeredby operationin the proposed manner,(2) suchactivitieswill be conductedin compliance with the Commission's regulations, and (3) the issuanceof the amendment will not be inimicalto the common defenseand securityor to the healthand safetyof the public.
5 . 0 E N V IR ON ME N T A L C ONSIDERATION The proposedamendmentwouldchangea requirement with respectto installation or use of a facilitycomponentlocatedwithinthe restrictedarea,as definedin 10 CFR 20, or wouldchangean inspectionor surveillance requirement.However,the proposed amendmentdoes not involve(i) a significanthazardsconsideration, (ii)a significant changein the typesor significantincreasein the amountsof any effluentsthat may be releasedoffsite,or (iii)a significantincreasein individualor cumulativeoccupational radiationexposure.Accordingly, the proposedamendmentmeetsthe eligibilitycriterion for categorical exclusionset forthin 10 CFR 51.22(c)(9).Therefore,pursuantto 10 CFR 51.22(b),no environmental impactstatementor environmental assessment needbe prepared in connectionwith the proposed amendment.
6.0 REFERENCES
1 . SafetyGuide9, "Selectionof DieselGeneratorSet Capacityfor Standby PowerSupplies," datedMarch10,1971.
2 . FirstEnergyNuclearOperatingCompanyLetterL-08-240,"Supplement to LicenseAmendmentRequest:Conversionof CurrentTechnicalSpecifications (C T S )to l mp ro ve T d e chnical ( lTS)- Volum es1,2,3,4,8, 10 ,
Specifications 12,13,14,and 16,TAC No.MD6398," datedAugust7,2008,Accession NumbersM1082270658 and ML082270669.
3 . FirstEnergy NuclearOperatingCompanyLetterL-08-338,"Copyof lmproved TechnicalSpecifications (lTS)TAC No. MD6398," datedOctober21,2008, AccessionNumberML08301 0076.
AttachmentA ProposedTechnicalSpecificationChanges PagesProvided.
The followingis a listof TechnicalSpecification 3 . 7 . 1 8- 1
- 3 . 7 . 1 8- 3 3.8.1-6 3.8.1-11
- No changesto this page. Pageprovidedfor informationonly.
No Changesto ThisPage, SteamGeneratorLevel 3.7.18 PageProvidedfor Information Only 3.7 PLANTSYSTEMS 3.7.18 SteamGeneratorLevel LCO3.7.18 Water Levelof each steamgeneratorshall be:
- a. Lessthanor equalto the maximumwaterlevelshownin Figure3.7.18-1 whenin MODE1 or 2;
- b. s 96% OperateRangewith LCO3.3.11,"Steamand FeedwaterRuptureControlSystem(SFRCS)
Instrumentation,"Function1 (MainSteamLinePressure-Low)not bypassedwhenin MODE3;
- c. s 96%OperateRangewithLCO3.3.11,Function1 bypassedand both mainfeedwater(MFW)pumpsnot capableof supplyingfeedwaterto the steamgenerators whenin MODE3: and
- d. S 50 inchesStartupRangewithLCO3.3.11,Function1 bypassedand one or bothMFW pumpscapableof supplyingfeedwaterto the steamgeneratorswhen in M O D E3 .
APPLICABILITY: M O D E S1 , 2 , a n d3 .
ACTIONS NOTE-------
Enterapplicable Conditions and Required Actionsof LCO3.1.1,"SHUTDOWN MARGIN (SDM),"when highsteamgeneratorwaterlevelresultsin exceedingthe SDM limits.
CONDITION REQUIRED ACTION COMPLETION TIME A. Water levelin one or A.1 Restoresteamgenerator 15 minutes more steamgenerators leveltowithinlimit.
notwithinlimits.
B . Required Actionand 8.1 Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Timenotmet. AND 8.2 Be in MODE4. 12hours Davis-Besse 3.7.18-1 Amendment 279
No Changesto ThisPage, SteamGeneratorLevel 3.7.18 PageProvidedfor Information Only SU R V E IL L A N CREE QUIR E ME NTS SURVEILLANCE FREQUENCY s R 3 . 7 . 1 8 . 1 Verifysteamgeneratorwaterlevelto be within limits.
Davis-Besse 3.7.18-2 Amendment279
SteamGeneratorLevel
-l
- <l Y
Jl UJI Al eo dl zl kl llnrccrptrblt ffiE0 Oprrrr.lng 8l Btg{ou 5l 3l 'o 3l 5oo ll Acctptlbl;
>l Ogrrrrlng xl
<l **glan
>l (page1 of 1)
Figure3.7.18-1 MaximumAllowableSteamGeneratorLevel Davis-Besse 3.7.18-3 Amendment279TBD
AC Sources- Operating 3.8.1 SURVEILLANCEREQUIREMENTS (continued SURVEILLANCE FREQUENCY sR 3.8.1.5 Checkfor and removeaccumulatedwaterfrom each 31 days daytank.
sR 3.8.1.6 Verifyintervalbetweeneach sequencedload block 31 days is withint 10o/oof designintervalfor each emergencyloadsequencerand eachemergency timedelayrelay.
sR 3.8.1.7 Verifythe fuel oil transfersystemoperatesto 92days transferfuel oil from fuel oil storagetank to the day tank.
sR 3.8.1.8 ---
- 'prelube
-;ilperiod.
il;;il; #3"'"=ffi ;;;ilil Verifyeach EDGstartsfromstandbyconditionand 184days achieves:
- a. In < 10 seconds,voltage> 40314070V and frequency> 58.8Hz; and
- b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5Hz.
Davis-Besse 3.8.1-6 Amendment279TBD
AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY sR 3.8.1.14
- t;ffi;;,,;;;; i
- ,153 ;;;;;,ilil--
5 minutesof shuttingdownthe EDGafterthe EDG has operated> t hourloaded> 2340kW and < 2600 kW.
Momentary transientsoutsideof loadrangedo not invalidate thistest.
- 2. All EDGstartsmay be precededby an engine prelubeperiod.
Verifyeach EDG startsand achieves: 24 months
- a. In < 10 seconds,voltage> 4Oe+4070V and frequency> 58.8 Hz; and
- b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5Hz.
Davis-Besse 3.8.1-11 Amendment279TBD
AttachmentB RetypedTechnicalSpecificationPages The followingis a listof the affectedpages.
3 . 7 . 1 8- 3 3.8.1-6 3.8.1-11
SteamGeneratorLevel 3.7.18 PageProvidedfor Information Only I
J IJJ I.IJ J
(,
z tr t
uJ tlrrrsccFirbla (L Op:rrtl,n3 o Buglou uJ J
m o
J J
l Accrptrth Oparrilng x irglon (0i&31 STEAMSUPERHEAT (OF)
Figure3.7.18-1(page1 of 1)
MaximumAllowableSteamGeneratorLevel Davis-Besse 3.7.18-3 Amendment TBD
PageProvidedfor Information Only AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued SURVEILLANCE FREQUENCY sR 3.8.1.5 Checkfor and removeaccumulatedwaterfrom each 31 days day tank.
sR 3.8.1.6 Verifyintervalbetweeneach sequencedload block 31 days is within! 10o/oof designintervalfor each emergencyloadsequencerand eachemergency timedelayrelay.
sR 3.8.1.7 Verifythe fuel oil transfersystemoperatesto 92 days transferfuel oil from fuel oil storagetank to the day tank.
sR 3.8.1.8 --
- i.6ilil;;il; prelubeperiod.
i3J"il;;;;;;;,;;-
Verifyeach EDG startsfrom standbyconditionand 184days achieves:
- a. ln < 10 seconds,voltage> 4070V and frequency> 58.8 Hz; and
- b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5 Hz.
Davis-Besse 3.8.1-6 AmendmentTBD
AC Sources- Operating PageProvidedfor Information Only 3.8.1 SURVEILLANCEREQUIREMENTS SURVEILLANCE FREQUENCY sR 3.8.1.14
- 1Tilil;;i:'15"';;;;;*il--
5 minutesof shuttingdownthe EDGafterthe EDG has operated> t hourloaded> 2340kW and < 2600 kW.
Momentary transientsoutsideof loadrangedo not invalidate thistest.
- 2. All EDGstartsmay be precededby an engine prelubeperiod.
Verifyeach EDG startsand achieves: 24 months
- a. ln < 10 seconds,voltage> 4070V and frequency> 58.8Hz; and
- b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5Hz.
Davis-Besse 3.8.1-11 AmendmentTBD