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Category:Letter type:LIC
MONTHYEARLIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0004, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2022-02-17017 February 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-21-0008, Organizational and Management Change2021-10-28028 October 2021 Organizational and Management Change LIC-21-0007, ISFSI Only Emergency Plan Update2021-09-0808 September 2021 ISFSI Only Emergency Plan Update LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report2021-04-29029 April 2021 Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-21-0003, Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report2021-03-30030 March 2021 Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-21-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-22022 February 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0015, Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092)2020-07-29029 July 2020 Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092) LIC-20-0014, Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2020-07-15015 July 2020 Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-20-0012, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2020-05-18018 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool LIC-20-0011, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-05-0707 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2020-04-30030 April 2020 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-20-0008, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-04-13013 April 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0006, (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2020-03-26026 March 2020 (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-03-10010 March 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-02-27027 February 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0002, Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan2020-02-27027 February 2020 Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan LIC-20-0001, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-02-0606 February 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0025, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-12-19019 December 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0007, Post-Shutdown Decommissioning Activities Report2019-12-16016 December 2019 Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-19-0022, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-11-18018 November 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0018, Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2019-11-14014 November 2019 Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-19-0020, Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis2019-10-17017 October 2019 Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis LIC-19-0017, Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 20042019-08-0808 August 2019 Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 An LIC-19-0010, License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associa2019-05-20020 May 2019 License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated LIC-19-0008, Submittal of 2018 Annual Report2019-04-0404 April 2019 Submittal of 2018 Annual Report LIC-19-0004, Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP)2019-03-28028 March 2019 Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP) LIC-19-0005, 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report2019-03-28028 March 2019 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2019-02-28028 February 2019 License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme LIC-19-0003, Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation R2019-02-28028 February 2019 Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation Requ LIC-19-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-01-0303 January 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-18-0031, Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update2018-12-17017 December 2018 Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update 2024-06-18
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARLIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML21271A5102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Am-241 Soil Uncertainty Report ML21271A1962021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3, 1, Omaha Public Power District, Defueled Safety Analysis Report CAC 2 ML21271A1802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 19, Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Characterization Report ML21271A2102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 4 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC 2 ML21271A1722021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 8 Omaha Public Power District, Offsite Dose Calculation Manual cac2 ML21271A1502021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Defueled Safety Analysis Report ML21271A4802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, C-14 Soil Uncertainty Report ML21271A2652021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 7 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A2682021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 12 FC-20-006, Rev 0, End State Concrete Surface Areas Volumes, CAC2 ML21271A5032021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Regression and Correlation Report ML21271A4982021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Uncertainty Report ML21271A1442021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS LTP Rev 0. Final - All ML21271A2582021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 8 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun -1 ML21271A2672021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC2 ML21271A2692021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 19 E. A. Napier, Hanford Environmental Dosimetry Upgrade Project, Gen II the Hanford Environmental Radiation D-1 ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML21271A2612021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 1 Haley & Aldrich, Hydrogeological Conceptual Site Model, Rev. 2, Fort Calhoun Station, Blair, Ne, 2021 CAC2 ML21271A2192021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 12 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A2622021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 2 Radiation Safety and Control Services, Tsd 20-001, Historical Site Assessment for Fort Calhoun Station - F-1 ML21271A2142021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 17 Omaha Public Power District, NO-FC-10, Quality Assurance Topical Report CAC2 ML21271A2592021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Copy of Calculations in Support of FCS LTP Chapter 6 Revision 0 ML21271A1932021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 18 Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Character 1 ML21271A1992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 16 Omaha Public Power District, Offsite Dose Calculation Manual CAC 2 ML21271A1832021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 11 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report cac2 ML21271A4082021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Eu-152 ML21271A1432021-08-0303 August 2021 License Amendment Request (LAR) 21-01, LIC-21-0005 LTP Cover Letter Final Fisher Signature ML21271A1732021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Omaha Public Power District, FCSD-RA-LT-100, Quality Assurance Project Plan for the License Termination Plan Development~1 ML21271A2002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 14 Backfill Attachment Final CAC 2 ML21271A1532021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 1 7 SUNSI EA 12-10, Flood Assessment HDR Report Placeholder Akb ML21271A1762021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 5 Omaha Public Power District, FCSD-RA-LT-200, Characterization Survey Plan CAC2 ML21271A2112021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 18 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A1752021-08-0202 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 14 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A2602021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 6 4, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2082021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 5, 10, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A1982021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 3, 6, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2132021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 5 9 Oddp FC-20-006 - End State Concrete Surface Areas and Volumes Rev 0 CAC2 ML21271A2062021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 4 10 Omaha Public Power District FC-20-006 - End State Concrete Surface Areas Volumes, Rev 0 CAC 2 ML21271A4452021-06-0505 June 2021 License Amendment Request (LAR) 21-01, FCS Embedded Pipe Dsr ML21271A2882021-06-0202 June 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Regression and Correlation Report Cm-244 ML21271A4362021-05-17017 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Pu-240 ML21271A3932021-05-16016 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Pu-240 ML21271A4062021-05-15015 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Cs-137 ML21271A4072021-05-15015 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Cs-137 ML21271A4142021-05-14014 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Np-237 ML21271A4392021-05-14014 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Cm-244 ML21271A4232021-05-14014 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Np-237 ML21271A3942021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Fe-55 ML21271A4102021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Pu-239 2024-06-18
[Table view] Category:Technical Specifications
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors LIC-15-0076, License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2015-09-11011 September 2015 License Amendment Request 15-06; Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. LIC-15-0085, License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item.2015-09-11011 September 2015 License Amendment Request 15-05; Application to Revise Technical Specification to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6B & 6C, Using the Consolidated Line Item. LIC-15-0053, License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes2015-08-20020 August 2015 License Amendment Request (LAR) 15-04; Application to Revise Technical Specification for Administrative Changes ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 LIC-14-0128, License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements2014-11-0707 November 2014 License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14115A2972014-04-10010 April 2014 Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML14041A4082014-02-10010 February 2014 License Amendment Request (LAR) 14-01, One-Time Extension of Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3 ML14108A0442013-12-31031 December 2013 Omaha Public Power District Fort Calhoun Station Unit Radiological Environmental Operating Report for Technical Specification Section 5.94.b January 1, 2013 to December 31, 2013 ML14108A0422013-12-31031 December 2013 Omaha Public Power District Fort Calhoun Station Unit No. 1 - Annual Report for Technical Specification Section 5.94.a January 1, 2013 to December 31, 2013 ML12128A1702012-04-12012 April 2012 Technical Specification (TS) Basis Change Index, Page 2 of 2 and TS 2.10 - Page 18 LIC-12-0006, License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO)2012-02-10010 February 2012 License Amendment Request (LAR) 12-01, Proposed Change to Establish the Reactor Protective System (RPS) Actuation Circuits Limiting Condition for Operation (LCO) LIC-12-0052, Annual Report for Technical Specification Section 5.9.4a2011-12-31031 December 2011 Annual Report for Technical Specification Section 5.9.4a LIC-10-0034, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.2010-07-12012 July 2010 License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c. LIC-10-0043, Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication2010-06-0101 June 2010 Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication ML0935611192010-01-22022 January 2010 Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications ML0925405912009-10-0909 October 2009 License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip ML0912502752009-05-0505 May 2009 Replacement Page TS 2.1 - Page 8, License Amendment Request for Administrative Revisions ML0907108912009-03-27027 March 2009 License Amendment, Issuance of Amendment No. 258, Revise Limiting Condition for Operation 2.7(2)j in TS 2.7, Electrical Systems, to Clarify Allowed Outage Time for Emergency Diesel Generators ML0911703682009-02-18018 February 2009 Updated Tech Spec Pages, from Licensee, License Amendment Request Lic 08-0078, Administrative Revisions to the Technical Specifications to Correct Typographical Errors and Provide Clarification LIC-09-0008, License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-01-30030 January 2009 License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. LIC-08-0074, License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)2008-07-31031 July 2008 License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT) LIC-08-0049, License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time2008-04-22022 April 2008 License Amendment Request (LAR) Clarification of Technical Specification (TS) 2.7(2)j, Regarding Emergency Diesel Generators Allowed Outage Time LIC-08-0008, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System.2008-02-0505 February 2008 License Amendment Request (LAR) Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System. LIC-07-0084, License Amendment Request, Change to Diesel Generator Surveillance Testing.2007-10-0505 October 2007 License Amendment Request, Change to Diesel Generator Surveillance Testing. LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent.2007-09-11011 September 2007 License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent. LIC-07-0046, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-05-16016 May 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707100982007-04-0303 April 2007 Technical Specifications, Editorial Changes to Apply Certain Limiting Conditions for Operation Requirements ML0705905082007-02-28028 February 2007 License and Technical Specification Pages - Amendment No. 248 to Facility Operating License Relocation of T.S. 2.22, Toxic Gas Monitors, and T.S. Table 3-3, Item 29 to Updated Safety Analysis Report LIC-06-0146, License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process.2006-12-20020 December 2006 License Amendment Request, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Purge System Using the Consolidated Line Item Improvement Process. LIC-06-0147, License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications2006-12-20020 December 2006 License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications ML0631105582006-11-0707 November 2006 Technical Specifications, Revising TS Steam Generator Tube Suveillance Program ML0631202592006-10-27027 October 2006 Tech Spec Pages for Amendment 244 Modifications to Technical Specification 2.4, Containment Cooling to Reduce Operable Containment Spray Pumps ML0628604282006-10-10010 October 2006 Response to Request for Additional Information (RAI) Related to the Replacement of Trisodium Phosphate ML0624304022006-08-30030 August 2006 Revised License Amendment Request, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Deletion of Sleeving as a Steam Generator.. ML0624201602006-08-30030 August 2006 Tech Spec Pages for Amendment 241 Regarding Use of M5 Fuel Cladding ML0624301302006-06-27027 June 2006 Tech Spec Pages for Amendment 240 Deletion of Design Features in Technical Specifications 4.3.1.2b and 4.3.1.2c LIC-06-0063, Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements.2006-06-0202 June 2006 Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements. 2024-01-31
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Omaha Public Power Oistdict 444 South 16th Street Mall Omaha NE 68102-2247 LIC-05-0113 December 19, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Reference:
Docket No. 50-285
SUBJECT:
Fort Calhoun Station, Unit No. 1, License Amendment Request, "Change to Diesel Generator Surveillance Testing" In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), the Omaha Public Power District (OPPD) is submitting a request for an amendment to the Fort Calhoun Station, Unit No. 1 (FCS) Technical Specifications (TSs). The proposed amendment requests a change to surveillance testing of the FCS diesel generators (DG) to support a modification to the DG start circuitry.
The modification (EC 33661) will be installed during an upcoming refueling outage scheduled to begin in September 2006. Modification EC 33661 will remove the anticipatory (idle-speed) DG start signals and allow only full speed DG starting on an under voltage condition. To ensure that the surveillance test accurately reflects the modification to the DG start circuitry, a change to TS 3.7(1)c.i is required. A footnote regarding a one-time surveillance interval extension for DG No.
1 is deleted as it is historical in nature and no longer necessary.
OPPD concludes that the proposed amendment presents no significant hazards considerations under the standards set forth in 10 CFR 50.92(c).
Attachment 1 provides a description of the proposed changes and confirmation of applicability.
Attachment 2 provides the existing TS pages marked-up to show the proposed changes.
Attachment 3 provides the proposed TS pages.
OPPD requests NRC approval by September 1, 2006 with an implementation period of no later than the end of the 2006 Refueling Outage currently scheduled to begin September 9, 2006.
No commitments to the NRC are made in this letter.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated State of Nebraska Official.
- t. _
Employment with Equal Opportunity
_7 __ . __ _ _ _. A._r_ __ X_1____
4171
U. S. Nuclear Regulatory Commission LIC-05-01 13 Page 2 I declare under penalty of perury that the foregoing is true and correct (Executed on December 19, 2005).
If you should have any questions regarding this submittal, please contact Tom Matthews at (402) 533-6938.
Sincerely, R. T. Ridenoure Vice Presiden t RTR/mle Attachments: 1. OPPD'sEvaluation
- 2. Markup of Technical Specification Pages-
- 3. Proposed Technical Specification Pages cc: Division Administrator - Public Health Assurance, State of Nebraska
LIC-05-01 13 Page 1 Omaha Public Power District's Evaluation For Amendment of Operating License
1.0 DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY SAFETY ANALYSIS 6.0 ENVIRONMENTAL EVALUATION
7.0 REFERENCES
LIC-05-0113 Page 2
1.0 DESCRIPTION
This letter is a request to amend Operating License DPR-40 for Fort Calhoun Station, Unit No. 1 (FCS).
During the 2006 refueling outage (RFO), Modification EC 33661 to the diesel generator (DG) starting circuitry will require a change to TS 3.7(1)c.i concerning DG surveillance testing requirements.
Modification EC 33661 (Reference 7.2) will remove the anticipatory (idle-speed)
DG start signals and allow only full speed DG starting on an under voltage condition. This modification requires a change to TS 3.7(1)c.i to ensure proper DG testing. Installation of the proposed modification will make FCS consistent with the rest of the industry and start the DGs only at full speed on under voltage conditions.
OPPD also proposes to remove a footnote to a one-time extension of the surveillance interval for DG No. 1 granted by Amendment 112 (Reference 7.3).
This one-time extension permitted the due date of the surveillance test to be extended from April 1988 to October 1988. This allowed the surveillance to be performed during a RFO since the performance of the surveillance during power operations could have resulted in the plant entering a limiting condition for operation (LCO) requiring a plant shutdown. This footnote is no longer pertinent and should be deleted.
For consistency with TS 3.7(1)c.i and 3.7(1)c.ii, a period is added immediately following TS 3.7(1)c.iii.
2.0 PROPOSED CHANGE
TS 3.7(1)c.i currently requires the initiation of a simulated auto-start signal to verify that the DG starts followed by the requirements of TS 3.7(1)c.ii for initiation of a simulated simultaneous loss of 4.16 KV supplies to Buses 1A3 and 1A4.
TS 3.7(1)c.i is revised to delete the words "followed by." Thus, TS 3.7(1)c will still require the initiation of a simulated auto-start signal to verify that the DG starts, but this will be concurrent with, not followed by, the simulated loss of 4.16 KV supplies to Buses 1A3 and 1A4 as required by TS 3.7(1)c.ii.
The change to TS 3.7(1)c.i is necessary to ensure verbatim compliance with TS 3.7(1)c during surveillance testing following installation of the modification. The proposed change will not affect current DG surveillance testing since the surveillance is performed at a refueling frequency and thus will not be performed until after the modification is installed during the 2006 RFO.
LIC-05-0113 Page 3 The footnote of TS 3.7(1)e is deleted in its entirety. The footnote pertains to a one-time extension of the surveillance interval for DG No. 1 granted by Amendment 112 (Reference 7.3). This footnote is no longer pertinent and should be deleted.
For consistency with TS 3.7(1)c.i and 3.7(1)c.ii, a period is added immediately following TS 3.7(1)c.iii.
3.0 BACKGROUND
The safety related DGs are required to perform their intended design function upon a loss of normal power to their respective 4.16 KV buses. The DGs are designed to automatically start, accelerate to rated speed, voltage and frequency and close on their respective bus as an emergency power source upon the loss of normal power.
Each DG is physically aligned to a 4.16 KV bus. DG-1 is aligned with Bus 1A3 and DG-2 is aligned with Bus 1A4. Normal power is from the 161 KV off-site power system transformed to 4.16 KV by Transformers T1A-3 and T1A-4 and supplied to Buses 1A3 and 1A4, respectively. In the event of an under voltage condition on either bus, the aligned DG automatically starts and provides emergency power. (Reference 7.1)
The original DG starting circuitry provided full speed DG starting on an under voltage condition and also provided several other anticipatory (idle speed) DG start signals. For example, an anticipatory (idle speed) start signal initiated by a reactor trip would start the DGs and accelerate them to idle speed in anticipation of a potential loss of power to the bus. Anticipatory (idle speed) DG starts were also provided for containment pressure high signal (CPHS) and pressurizer pressure low signal (PPLS).
The design basis for the anticipatory (idle speed) DG start is not definitively stated in FCS licensing or design basis documents. It is apparently a precautionary step to ensure that the DGs are already running (at idle speed) following a design basis accident (DBA) in the event that a subsequent loss of offsite power should occur. However, there is no design criterion or regulatory requirement for the DGs to be operating at idle speed following a DBA nor does any Updated Safety Analysis Report (USAR) accident analysis take credit for the anticipatory (idle speed) DG start following a DBA.
Modification EC 33661 removes the anticipatory (idle speed) DG start signals such that the DGs start and accelerate to full speed and then only on an under voltage condition. Removal of the anticipatory (idle speed) DG start signals does not change the function of the DGs as they still provide emergency power to their respective buses when required.
LIC-05-0113 Page 4 The proposed amendment to TS 3.7(1)c.i is necessary to accurately reflect actual surveillance testing of the DGs following removal of the anticipatory (idle speed) start signals. Due to the elimination of anticipatory (idle speed) starts, the initiation of a simulated simultaneous loss of 4.16 KV supplies to Bus 1A3 (or Bus 1A4 depending on which DG is being tested) will now occur simultaneously with the simulated auto-start signal. Prior to Modification EC 33661, the simulated auto-start signal verifying that the DG starts (to idle speed) was followed by the simulated simultaneous loss of 4.16 KV power to the bus whose DG was being tested (Bus 1A3 or 1A4).
The footnote to TS 3.7(1)e was placed into the FCS TSs by Amendment 112 (Reference 7.3) to permit a one-time extension of the surveillance interval for DG No. 1. Diesel generators are tested at 18-month intervals to be consistent with the maximum anticipated interval between refueling outages. The selection of an 18 month interval was based on engineering judgment to achieve the dual goals of the need to conduct periodic surveillance tests but not interfere substantially with unit availability.
OPPD requested and was granted a one-time extension of the surveillance test interval from April 1988 to October 1988 to coincide with the 1988 RFO. The extension was granted (Reference 7.3) because performance of the surveillance in April 1988 would have been during power operations that could have resulted in the plant entering a LCO requiring a plant shutdown. Since the footnote is historical in nature, it is unnecessary and should be deleted.
The addition of a period following TS 3.7(1)c.iii is an administrative change to achieve consistent punctuation.
4.0 TECHNICAL ANALYSIS
Currently, TS 3.7(1)c.i has a provision to test the DGs using a simulated auto-start signal to verify that the diesel starts. An anticipatory start signal simulates this function and starts the DG at idle speed. TS 3.7(1)c.i states that this is followed by the initiation of a simulated simultaneous loss of 4.16 KV power to Bus 1A3 or Bus 1A4 (depending on which DG is being tested) the purpose of which is to de-energize the bus and verify DG emergency loading.
The proposed amendment to TS 3.7(1)c.i removing the words "followed by" is necessary to accurately reflect actual surveillance testing of the DGs following removal of the anticipatory (idle speed) start signals. The design basis for the anticipatory (idle speed) DG start is concluded to be a precautionary step to ensure that the DGs are already running (at idle speed) following a design basis accident (DBA) in the event that a subsequent loss of offsite power should occur.
However, there is no design criterion or regulatory requirement for the DGs to be
LIC-05-01 13 Page 5 operating at idle speed following a DBA nor does any USAR accident analysis take credit for the anticipatory (idle speed) DG start following a DBA.
Due to the elimination of anticipatory (idle speed) starts, the initiation of a simulated simultaneous loss of 4.16 KV power to Bus 1A3 (or Bus 1A4 depending on which DG is being tested) will now occur simultaneously with the simulated auto-start signal. Prior to Modification EC 33661, the simulated auto-start signal verifying that the DG starts (to idle speed) was followed by the simulated simultaneous loss of 4.16 KV power to the bus whose DG was being tested (Bus 1A3 or 1A4).
The Basis of TS 3.7 explains that automatic starting on loss of off-site power and automatic load shedding, diesel connection, and loading will be verified on a refueling frequency. Modification EC 33661 does not affect the basis of TS 3.7, which is still accurate in this regard.
Deletion of the TS 3.7(1)e footnote is an administrative change that removes a surveillance interval extension that is historical in nature and no longer serves a purpose in the FCS TSs.
The addition of a period following TS 3.7(1)c.iii is an administrative change to achieve consistent punctuation.
In summary, the proposed changes do not alter, degrade, or prevent actions described or assumed in any accident analysis. The proposed changes do not revise any previous assumptions evaluating radiological consequences or affecting any fission product barriers, nor do they increase any challenges to safety systems. Therefore, the proposed changes do not increase or have any impact on the consequences of events described and evaluated in Chapter 14 of the FCS Updated Safety Analysis Report (USAR).
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration OPPD has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
LIC-05-01 13 Page 6 The removal of the anticipatory (idle speed) diesel generator (DG) start signals does not adversely affect the design function of the DGs and thus is not an initiator of any previously evaluated accidents. No Updated Safety Analysis Report (USAR) accident analyses take credit for the anticipatory (idle speed) DG start following a design basis accident (DBA). The DGs provide emergency power to their respective 4.16 KV buses and will continue to do so after the proposed modification is installed. Upon the occurrence of an under voltage condition on the bus, the modification provides a full speed DG start to achieve rated voltage and frequency. The safety function of the DGs is not altered by the installation of this modification. The associated TS change allows surveillance testing to reflect the way that the DGs start and load onto their respective buses following the modification.
Deletion of a footnote containing historical information pertaining to a one-time surveillance interval extension and the punctuation correction are administrative changes that do not increase the probability or consequences of any accident previously evaluated.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of any accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The removal of the anticipatory (idle speed) diesel generator (DG) start signals does not adversely affect the design function of the DGs and thus does not create the possibility of a new or different kind of accident. No USAR accident analyses take credit for the anticipatory (idle speed) DG start following a DBA. The DGs provide emergency power to their respective 4.16 KV buses and will continue to do so after the proposed modification is installed. Upon the occurrence of an under voltage condition on the bus, the modification provides a full speed DG start to achieve rated voltage and frequency. The safety function of the DGs is not altered by the installation of this modification. The associated TS change allows surveillance testing to reflect the way that the DGs start and load onto their respective buses following the modification.
Deletion of a footnote containing historical information pertaining to a one-time surveillance interval extension and the punctuation correction are administrative changes that do not create the possibility of a new or different kind of accident from any previously evaluated.
LIC-05-01 13 Page 7 Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The removal of the anticipatory (idle speed) diesel generator (DG) start signals does not adversely affect the design function of the DGs and thus does not involve a significant reduction in a margin of safety. No USAR accident analyses take credit for the anticipatory (idle speed) DG start following a DBA. The DGs provide emergency power to their respective 4.16 KV buses and will continue to do so after installation of the proposed modification. Upon the occurrence of an under voltage condition on the bus, the modification provides a full speed DG start to achieve rated voltage and frequency. The safety function of the DGs is not altered by the installation of this modification. The associated TS change allows surveillance testing to reflect the way that the DGs will start and load onto their respective buses following the modification.
Deletion of a footnote containing historical information pertaining to a one-time surveillance interval extension and the punctuation correction are administrative changes that do not reduce a margin of safety.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, OPPD concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements/Criteria FCS was licensed for construction prior to May 21, 1971, and at that time committed to the draft General Design Criteria (GDC). The draft GDC are contained in Appendix G of the FCS USAR and are similar to 10 CFR 50 Appendix A, General Design Criteria for Nuclear Power Plants. The draft GDC that govern emergency power are Criterion 24 and Criterion 39 from USAR Appendix G.
Criterion 24 - Emergency power for Protection Systems, states:
LIC-05-01 13 Page 8 "In the event of loss of all offsite power, sufficient alternate sources of power shall be provided to permit the required functioning of the protection systems."
This criterion is met. Emergency power is available from two completely independent diesel generator (DG) sets and from two completely independent 125 V d-c systems for essential d-c loads.
The independent diesel generator supply systems are located in the plant and are connected to separate buses. Both generator sets independently start automatically upon loss of auxiliary power and are ready to accept load within 10 seconds of loss of normal supply power. Starting power is self-contained within each DG. Each DG has sufficient capacity to start in sequence the loads required for the engineered safeguards equipment for the maximum hypothetical accident concurrent with loss of outside power. This capacity is adequate to provide a safe and orderly plant shutdown and maintain the plant in a safe condition.
Each of the two 125 V d-c batteries is capable of supplying essential station d-c loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and may be charged by the generator power supply.
Facilities are included to permit periodic starting and running of the DGs without interrupting plant operation. The DGs are synchronized to the bus and loaded periodically to ensure readiness for emergency services.
Criterion 39 - Emergency Power For Engineered Safety Features states:
"Alternate power systems shall be provided and designed with adequate independency, redundancy, capacity and testability to permit the functioning required of the engineered safety features. As a minimum, the onsite power system and the offsite power system shall each independently provide this capacity assuming a failure of a single active component in each power system."
This criterion is met. Offsite power to the plant is available via the 161 kV line and after the unit is tripped, via backfeed from the 345 kV system through the main and unit auxiliary transformers.
When the unit is tripped and the 161 kV supply is not available, the motor-operated disconnect switch in the generator main leads is opened and the supply to the unit auxiliary transformers is re-established. Switch operation is accomplished by a motor operator supplied from the station battery. Onsite power is provided by two diesel generator sets. Each independent diesel generator set is adequate for supplying the minimum engineered safeguards equipment for the maximum hypothetical accident concurrent with loss of outside power.
LIC-05-01 13 Page 9 Station batteries provide onsite power for instrument and control systems. These batteries are subject to rigorous inspection and maintenance. Periodically, the charger voltage is manually lowered to test the batteries capability to assume load at the appropriate bus voltage.
The diesel generator facilities permit periodic starting and running during normal plant operations.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulation, and (3) the issuance of amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amount 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.
7.0 REFERENCES
7.1 USAR Sections 7.3.4.2, 8.4.1, 8.3.4 & 8.4.2 7.2 Modification EC 33661 "Diesel Generator DG-1 & DG-2 Governor Change" 7.3 Letter from NRC (A. Bournia ) to OPPD (R. L. Andrews ) dated April 19, 1988, "Fort Calhoun Station, Unit No. 1 - Amendment No. 112 to Facility Operating License No. DPR-40 (TAC No. 67466)
LIC-05-01 13 Page 1 MARKUP OF TECHNICAL SPECIFICATION PAGE
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.7 Emergency Power System Periodic Tests (Continued)
- i. <<>on of a simulated auto-start signal to verify that the diesel starqlt ii. Initiation of a simulated simultaneous loss of 4.16 KV supplies to bus 1A3 (1A4). Proper operation will be verified by observation of:
(1) De-energization of bus 1A3 (1A4).
(2) Load shedding from bus (both 4160 V and 480 V).
(3) Energization of bus 1A3 (1A4).
(4) Automatic sequence start of emergency load, and (5) Operation of > 5 minutes while its generator is loaded with the emergency load.
ii4) Verification that emergency loads do not exceed the 2000-HR KW rating of the V'-' engine.(2)
- d. Manual control of diesel generators and breakers shall also be verified during refueling shutdowns.
- e. Each diesel generator shall be given a thorough inspection on a refueling (R) frequency in accordance with the manufacturer's recommendations for this class of standby servicg:7)
- f. The fuel oil transfer pumps shall be verified to be operable each month.
(2) Station Batteries
- a. Every month the voltage of each cell (to the nearest 0.01 volt), the specific gravity, and temperature of a pilot cell in each battery shall be measured and recorded.(3 )
- b. Every three months the specific gravity of each cell, the temperature reading of every fifth cell, and the amount of water added shall be measured and recorded. During the first refueling outage and every third refueling outage thereafter the batteries shall be subjected to a rated load discharge test.
- c. At monthly intervals the third battery charger, which is capable of being connected to either of the two D.C. distribution buses, shall be paralleled in turn to each D.C. bus.
In each case, load shall be transferred to this reserve battery charger by switching out the normal charger. The reserve charger shall be run on load for 30 minutes on each bus and the system shall finally be returned to normal.
g~;extns en has been granted for-this surveillancf euieet allowingte p.
ferao No. 1 to be cempleted innt Otb 1M.
3.7 - Page 2 Amendment No. -24,444,1 LIC-05-01 13 Page 1 PROPOSED TECHNICAL SPECIFICATION PAGE
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.7 Emergency Power System Periodic Tests (Continued)
- i. Initiation of a simulated auto-start signal to verify that the diesel starts.
ii. Initiation of a simulated simultaneous loss of 4.16 KV supplies to bus 1A3 (1A4).
Proper operation will be verified by observation of:
(1) De-energization of bus 1A3 (1A4).
(2) Load shedding from bus (both 4160 V and 480 V).
(3) Energization of bus 1A3 (1A4).
(4) Automatic sequence start of emergency load, and (5) Operation of > 5 minutes while its generator is loaded with the emergency load.
iii. Verification that emergency loads do not exceed the 2000-HR KW rating of the engine. 2 )
- d. Manual control of diesel generators and breakers shall also be verified during refueling shutdowns.
- e. Each diesel generator shall be given a thorough inspection on a refueling (R) frequency in accordance with the manufacturer's recommendations for this class of standby service.
- f. The fuel oil transfer pumps shall be verified to be operable each month.
(2) Station Batteries
- a. Every month the voltage of each cell (to the nearest 0.01 volt), the specific gravity, and temperature of a pilot cell in each battery shall be measured and recorded.(3 4)(
- b. Every three months the specific gravity of each cell, the temperature reading of every fifth cell, and the amount of water added shall be measured and recorded. During the first refueling outage and every third refueling outage thereafter the batteries shall be subjected to a rated load discharge test.
- c. At monthly intervals the third battery charger, which is capable of being connected to either of the two D.C. distribution buses, shall be paralleled in turn to each D.C. bus. In each case, load shall be transferred to this reserve battery charger by switching out the normal charger. The reserve charger shall be run on load for 30 minutes on each bus and the system shall finally be returned to normal.
3.7 -Page 2 Amendment No. 24,1-14,142