|
---|
Category:Letter type:LIC
MONTHYEARLIC-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 LIC-18-0030, Request for Partial Site Release Phase 22018-11-12012 November 2018 Request for Partial Site Release Phase 2 LIC-18-0028, Letter of Intent to Submit Request for Additional Partial Site Release2018-10-18018 October 2018 Letter of Intent to Submit Request for Additional Partial Site Release LIC-18-0027, Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2018-10-0303 October 2018 Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update LIC-18-0003, License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool2018-09-28028 September 2018 License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool LIC-18-0025, Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 20192018-07-19019 July 2018 Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 2019 LIC-18-0023, Fort Calhoun Station, Unit 1 Request for Partial Site Release2018-06-29029 June 2018 Fort Calhoun Station, Unit 1 Request for Partial Site Release LIC-18-0021, Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan)2018-06-0606 June 2018 Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan) LIC-18-0017, Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy2018-04-26026 April 2018 Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy 2023-08-24
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML21271A4982021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Uncertainty Report 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 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 ML21271A1442021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS LTP Rev 0. Final - All ML21271A5102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Am-241 Soil Uncertainty Report 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 ML21271A1532021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 1 7 SUNSI EA 12-10, Flood Assessment HDR Report Placeholder Akb ML21271A4082021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Eu-152 ML21271A1992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 16 Omaha Public Power District, Offsite Dose Calculation Manual CAC 2 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 ML21271A2002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 14 Backfill Attachment Final 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 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 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 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 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 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 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 ML21271A3972021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Sb-125 ML21271A4012021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report H-3 ML21271A3942021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Fe-55 ML21271A4032021-05-13013 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Cm-243 2021-08-03
[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 ML0624201602006-08-30030 August 2006 Tech Spec Pages for Amendment 241 Regarding Use of M5 Fuel Cladding 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.. 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
[Table view] |
Text
Fort Calhoun Station P.O. Box 550 Fort Calhoun, NE 68023 April 22, LI U.s. Nuclear Regulatory Attn: Document Control Mail Station Washington, DC
References:
- 1. Docket No. 50-285 2. Letter from OPPD (R. P. Clemens) to NRC (Document Control Desk), Clarification of Fort Calhoun Station Technical Specification 2.7(2)j, dated February 20,2008 (L1C-08-0012)
Fort Calhoun Station, Unit No.1, License Amendment Request (LAR) "Clarification of Technical Specification (TS) 2.7(2)j Regarding Emergency Diesel Generators Allowed Outage Time" Pursuant to 10 CFR 50.90, and in accordance with a commitment made in Reference 2, the Omaha Public Power District (OPPD) hereby requests an amendment to Fort Calhoun Station (FCS), Unit No.1, Renewed Facility Operating License No. DPR-40. The enclosed license amendment request (LAR) clarifies TS 2.7(2)j regarding emergency diesel generator (DG) allowed outage time (AOT). The enclosure contains a description of the proposed changes, the supporting technical analyses, and the significant hazards consideration determination.
Attachment 1 provides the existing TS page marked-up to show the proposed changes. Attachment 2 provides the retyped (clean) TS page. OPPD has determined that this LAR does not involve a significant hazard consideration as determined per 10 CFR 50.92. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of this amendment.
There are no regulatory commitments associated with this proposed change. OPPD requests approval by April 1, 2009, with a 120-day implementation period. In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated State of Nebraska Official.
U. S. Nuclear Regulatory Commission LIC-08-0049 Page 2 If you should have any questions regarding this submittal, please contact Mr. Thomas C. Matthews at (402) 533-6938.
I declare under penalty of perjury that the foregoing is true and correct. (Executed on April 22, 2008.)
D. J. Bannister Vice President DJB/MLE/mle
Enclosure:
OPPD's Evaluation of the Proposed Changes Director of Consumer Health Services, Department of Regulation and Licensure, Nebraska Health and Human Services, State of Nebraska LIC-08-0049 Enclosure Page 1 Omaha Public Power District's Amendment of Operating "Clarification of Technical Specification (TS) 2.7(2)j Regarding Emergency Generators Allowed Outage 1.0
SUMMARY
DESCRIPTION
2.0 DETAILED
DESCRIPTION
3.0 TECHNICAL
EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria
4.2 Precedent
4.3 Significant
Hazards Consideration
4.4 Conclusions
5.0 ENVIRONMENTAL
CONSIDERATION
6.0 REFERENCES
ATIACHMENTS:
- 1. Technical Specification Page (Mark-up of Proposed Changes) 2. Proposed Technical Specification Page (Clean)
L1C-08-0049 Enclosure Page 2
SUMMARY
DESCRIPTION The Omaha Public Power District (OPPD) hereby requests an amendment to Fort Calhoun Station (FCS), Unit No.1, Renewed Facility Operating License No. DPR-40 to incorporate the attached change into the FCS Technical Specifications (TS). The proposed change would revise the Operating License to clarify the allowed outage time (AOT) for the emergency diesel generators (DGs). As such, changes are proposed for TS 2.7(2)j. DETAILED DESCRIPTION At the end of January 2008, DG-2 entered a planned maintenance outage and complications during the outage threatened to delay its restoration beyond the 7-day AOT of TS 2.7(2)j. Therefore, on February 1, 2008, OPPD contacted NRC Region IV to inquire about enforcement discretion to extend the AOT for DG-2 past the allowed 7 days (ultimately, DG-2 was restored to operability within the 7-day AOT). The NRC informed OPPD that enforcement discretion would be difficult to grant because the AOT of TS 2.7(2)j was ambiguous particularly when periods of inoperability span calendar months. As a result of that event, OPPD committed to clarify TS 2.7(2)j regarding how the TS limits periods of DG inoperability to seven days or less. It should be noted that OPPD has internal procedural guidance ensuring appropriate application of the TS consistent with its intent to limit periods of DG inoperability to seven days or less. OPPD proposes to clarify TS 2.7(2)j such that a single period of inoperability for one DG is limited to seven consecutive days and specify that the cumulative total time of inoperability for both DGs during any calendar month cannot exceed seven days. The proposed revision to TS 2.7(2)j requires both conditions to be met. Specifically, TS 2.7(2)j will be revised as follows (new text is underlined, deleted text is in strikeout): Either one of the emergency diesel generators (DG-1 or DG-2) may be inoperable for up to seven consecutive days (total for both) during any month, provided there are no inoperable required engineered safeguards components associated with the operable diesel generator and the cumulative total time of inoperabilitv for both DGs during any calendar month does not exceed seven days. If one diesel generator is inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (regardless of when the inoperable diesel generator is restored to operability)
EITHER: Start the other diesel generator to verify operability, OR Ensure the absence of common cause for the diesel generator inoperability for the other diesel generator.
L1C-08-0049 Enclosure Page 3 3. TECHNICAL EVALUATION TS 2.7 applies to the availability of electrical power for the operation of plant components and defines those conditions of electrical power availability necessary to provide for safe reactor operation and continued availability of engineered safeguards equipment.
As such, TS 2.7(1)1 does not allow the reactor to be heated up or maintained at temperatures above 300°F unless DG-1 and DG-2 are operable.
These independent DG systems are located in the plant and are connected to separate buses. Both generator sets are independent and start automatically upon loss of offsite power. The diesel generators are ready to accept load within 10 seconds of loss of normal power supply (Le., offsite power). Starting power is self-contained within each unit. Each unit has sufficient capacity to start sequentially the loads that must be supplied for the engineered safeguards equipment for the design basis accident (DBA) 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.
Since FCS has sufficient DG capacity and redundancy, TS 2.7(2)j permits TS 2.7(1)1 to be modified such that one of the DGs may be inoperable for up to seven days to allow for maintenance and/or testing. The 7-day AOT of TS 2.7(2)j dates from the original issuance of the operating license in 1973. Regulatory requirements that did not exist at that time now supplement the requirements of TS 2.7(1)1 and help to ensure that both DGs are OPERABLE when the reactor is heated up or maintained at temperatures above 300°F. These programs are The Maintenance Rule (10 CFR 50.65(a)(1))
and the reactor oversight process (ROP). The Maintenance Rule: 10 CFR 50.65(a)(1), the Maintenance Rule, requires each licensee to monitor the performance or condition of structures, systems, and components (SSCs) against licensee-established goals to ensure that the SSCs are capable of fulfilling their intended functions.
If the performance or condition of an SSC does not meet established goals, appropriate corrective action is required to be taken. The NRC Resident Inspectors monitor OPPD's Corrective Action Process and could take action if OPPD's maintenance program routinely permitted TS 2.7(2)j to circumvent the TS 2.7(1)1 requirement to have both DGs operable.
The performance and condition monitoring activities required by 10 CFR 50.65(a)(1) and (a)(2) would identify if poor maintenance practices resulted in multiple entries into the LCO and unacceptable DG availability.
The effectiveness of these performance monitoring activities, and associated corrective actions, is evaluated at least every refueling cycle, not to exceed 24 months, per 10 CFR 50.65(a)(3).
The Maintenance Rule (10 CFR 50.65(a)(4)), considers all inoperable risk-significant equipment, not just the one or two systems governed by the same LCO. Under 10 CFR 50.65(a)(4), the risk impact of all inoperable risk-significant equipment is assessed and managed when performing preventative or corrective maintenance.
The risk assessments are conducted using the procedures and guidance endorsed by L1C-08-0049 Enclosure Page 4 Regulatory Guide 1.182, Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants. Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed maintenance is acceptable.
This comprehensive program provides assurance of safe plant operation.
The Reactor Oversight Process, NEI 99-02, Regulatory Assessment Performance Indicator Guideline, describes the tracking and reporting of performance indicators to support the NRC's ROP. The NEI document is endorsed by Regulatory Issue Summary (RIS) 2001-11, Voluntary Submission of Performance Indicator Data. NEI 99-02, Section 2.2, describes the Mitigating Systems Cornerstone.
NEI 99-02 specifically addresses emergency AC sources. Extended unavailability of the emergency AC sources (i.e., diesel generators) due to multiple entries into TS 2.7(2)j would affect the NRC's evaluation of OPPD's performance under the ROP, which represents a strong disincentive for such operation.
Based on the above discussion, the concern regarding multiple continuous entries into 2.7(2)j without meeting the LCO of TS 2.7(1)1 is addressed by the system unavailability monitoring programs described above. Therefore, this potential concern is not an issue. Specifying that a single period of inoperability for one DG is limited to seven consecutive days and stating that the cumulative total time of inoperability for both DGs during any calendar month cannot exceed seven days clarifies TS 2.7(2)j but does not make it less restrictive.
Therefore, these clarifications and editorial changes are not detrimental to plant safety.
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria 10 CFR 50.36 Technical Specifications.
10 CFR 50.36(c)(2) states, "When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met." The revised actions continue to meet the requirements of this regulation.
L1C-08-0049 Enclosure Page 5 10 CFR 50.65" Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. The overall objective of this performance-based rule is to ensure that nuclear power plant structures, systems, and components (SSCs) will be maintained so that they will perform their intended function when required.
The revised actions continue to meet the requirements of this regulation.
General Design 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 Updated Safety Analysis Report (USAR). Criterion 24 -Emergency Power for Protection Systems is applicable to this LAR and states: 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 sets and from the two completely independent 125v dc systems for essential dc loads. The independent diesel generator supply systems are located in the plant and are connected to separate buses. Both generator sets are independently automatic starting upon loss of auxiliary power and will be ready to accept load within 10 seconds of loss of normal supply power. Starting power is self-contained within each unit. Each unit has sufficient capacity to start sequentially the loads that must be supplied for the engineered safeguards equipment for the 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 125v dc batteries is capable of supplying essential station dc load 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 the Diesel generator sets without interrupting plant operation.
Diesel units are synchronized to the bus and loaded periodically to ensure readiness for emergency services.
The revised actions continue to meet the requirements of Criterion
- 24. 4.2 Precedent None.
L1C-08-0049 Enclosure Page 6 4.3 Significant Hazards Consideration The Technical Specifications (TSs) for Fort Calhoun Station (FCS), Unit No. 1 are modified to clarify the allowed outage time (AOT) of TS 2.7(2)j for the emergency diesel generators (DGs) but are not less restrictive.
The Omaha Public Power District (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 10 CFR 50.92, "Issuance of amendment," as discussed below: Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No. The proposed changes clarify the AOT of TS 2.7(2)j for DG inoperability but are not less restrictive.
Allowed outage times and editorial changes such as these are not an initiator of any accident previously evaluated.
As a result, the probability of an accident previously evaluated is not affected.
The consequences of an accident during the revised AOT are no different than the consequences of the same accident during the existing AOT. As a result, the consequences of an accident previously evaluated are not affected by these changes. The proposed changes do not alter or prevent the ability of structures, systems, and components from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed changes do not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated.
Further, the proposed changes do not increase the types or amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/public radiation exposures.
The proposed changes are consistent with the safety analysis assumptions and resultant consequences.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Does the proposed change create the possibility of a new or different accident from any accident previously evaluated?
Response:
No. The proposed changes do not involve a physical alteration of the plant (Le., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.
The proposed changes do not alter any assumptions made LIC-08-0049 Enclosure Page 7 in the safety analysis.
Therefore, the proposed changes do not create the possibility of a new or different accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety? Response:
No. The proposed changes clarifying the AOT of TS 2.7(2)j for DG inoperability do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined.
The safety analysis acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation in a configuration outside of the design basis. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
4.4 CONCLUSION
S Based on the considerations disclJssed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Therefore, OPPD concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.
5.0 ENVIRONMENTAL
CONSIDERATION OPPD has evaluated the proposed amendment and has determined that the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0. REFERENCES
None.
Attachment Page Technical Specification (Mark-up of Proposed TECHNICAL SPECIFICATIONS LIMITING CONDITIONS FOR OPERATION Electrical Systems (Continued) Either one of the 4.16kV engineered safeguards buses, 1A3 or 1A4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the operability of the diesel generator associated with the operable bus is demonstrated immediately and there are no inoperable required engineered safeguards components associated with the operable bus. One of each group of 4160 V/480 V Transformers (T1 B-3A or 4A), (T1 B-3B or 4B), and (1'1 B-3C or 4C) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required engineered safeguards components which are redundant to components on the inoperable transformer. One of the 480 V distribution buses connected to bus 1 A3 or connected to bus 1A4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required safeguards components which are redundant to components on the inoperable bus. Either Group of MCC No.'s (3A1, 3B1, 3A2, 3C1, 3C2,) or (4A1, 4A2, 4C1, 4C2) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required safeguards components which are redundant to components on the inoperable MCC. MCC 3C1 may be inoperable in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if battery chargers NO.1 and NO.2 are operable. One of the four 120V a-c instrument buses (A, B, C or D) may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the reactor protective and engineered safeguards systems instrument channels supplied by the remaining three buses are all operable. Two battery chargers may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided battery charger NO.1 (EE-8C) or NO.2 (EE-8D) is operable. Either one of the emergency diesel generators (DG-1 or DG-2) may be inoperable for up to seven consecutive days (total for both) during any month, provided there are no inoperable required engineered safeguards components associated with the operable diesel generator and the cumulative total time of inoperability for both DGs during any calendar month does not exceed seven days. If one diesel generator is inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (regardless of when the inoperable diesel generator is restored to operability)
EITHER: Start the other diesel generator to verify operability, OR Ensure the absence of common cause for the diesel generator inoperability for the other diesel generator. Not used. 2.7 -Page Amendment No. 60,147,150, 162,213, 229
Attachment Page Proposed Technical Specification TECHNICAL SPECIFICATIONS LIMITING CONDITIONS FOR OPERATION Electrical Systems (Continued)
- d. Either one of the 4.16kV engineered safeguards buses, 1A3 or 1A4 e.
(T18-38 or 48), and (T18-3C or 4C) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required engineered safeguards components which are redundant to components on the inoperable transformer. One of the 480 V distribution buses connected to bus 1 A3 or connected to bus 1 A4 may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required safeguards components which are redundant to components on the inoperable bus. Either Group of MCC No.'s (3A1, 381, 3A2, 3C1, 3C2,) or (4A1, 4A2, 4C1, 4C2) may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required safeguards components which are redundant to components on the inoperable MCC. MCC 3C1 may be inoperable in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if battery chargers No.1 and No.2 are operable. One of the four 120V a-c instrument buses (A, 8, C or D) may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the reactor protective and engineered safeguards systems instrument channels supplied by the remaining three buses are all operable. Two battery chargers may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided battery charger No.1 (EE-8C) or No.2 (EE-8D) is operable. Either one of the emergency diesel generators (DG-1 or DG-2) may be inoperable for up to seven consecutive days provided there are no inoperable required engineered safeguards components associated with the operable diesel generator and the cumulative total time of inoperability for both DGs during any calendar month does not exceed seven days. If one diesel generator is inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (regardless of when the inoperable diesel generator is restored to operability)
EITHER: Start the other diesel generator to verify operability, OR Ensure the absence of common cause for the diesel generator inoperability for the other diesel generator. Not used. 2.7 -Page Amendment No. 60,147,150, 162,213,229