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MONTHYEARML0302201432003-01-16016 January 2003 Issuance of Amendment No. 214, Relocation of Nuclear Detector Cooling Technical Specification 2.13 to Updated Safety Analysis Report Project stage: Approval 2003-01-16
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Category:Letter
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 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 IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 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 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 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 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 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 IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities 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 ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22159A2152022-06-28028 June 2022 Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan 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 IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 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 2024-01-31
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements ML20071E1042020-03-25025 March 2020 Issuance of Amendment to Change the Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan to Reflect an ISFSI-Only Configuration ML19297D6772019-12-11011 December 2019 Issuance of Amendment to Revise the Permanently Defueled Technical Specifications to Align to the Requirements for Permanent Removal of Spent Fuel from the Spent Fuel Pool ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18068A1652018-03-0909 March 2018 Correction to Page 1 of Attachment to Enclosure 1 for Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17179A1782017-06-29029 June 2017 Correction to Technical Specification Definitions - Page 7 for Amendment No. 286, Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and ... LIC-17-0047, Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2017-05-15015 May 2017 Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16182A3632016-08-19019 August 2016 Issuance of Amendment No. 289, Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML16139A8042016-06-0808 June 2016 Issuance of Amendment No. 288, Request to Adopt Technical Specifications Task Force (TSTF)-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6b & 6c 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 ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date 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 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) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1015202962010-06-0202 June 2010 License Amendment, Issuance of Amendment No. 265, Revise Technical Specification 2.15, Table 2-5, Note C for Safety Valve Acoustic Position Indication (Emergency Circumstances) ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e 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 ML0919005692009-07-24024 July 2009 Unit No.1 - Issuance of Amendment No. 261, Modify Transformer Allowed Outage Time in Technical Specification 2.7(2) and Delete Associated 2.7(2) Special Reporting Requirements in TS 5.9.3j ML0916205692009-07-24024 July 2009 Issuance of Amendment 262, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0912801022009-07-22022 July 2009 Issuance of Amendment No. 260, Modification of Surveillance Requirements in TS 3.6(3), Containment Recirculating Air Cooling and Filtering System & Removal of License Conditions ML0832606972009-05-12012 May 2009 Issuance of Amendment No. 259, Revise Technical Specifications to Correct Typographical Errors and Make Administrative Clarifications 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 ML0730903612007-12-17017 December 2007 Issuance of Amendment No. 251, Modify Technical Specification Requirements to Support Addition of Safety-Related Swing Inverters to 120 Volt AC Buses ML0720400972007-07-26026 July 2007 Conforming License Amendment to Incorporate the Mitigation Strategies of Commission Order EA-02-026 (Tac No. MD4534) ML0720402832007-07-26026 July 2007 Revised Pages of Facility Operating License DPR-40 to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 ML0706102692007-06-0606 June 2007 Issuance of Amendment No. 250 Adoption of TSTF-447 to Delete Requirements for Hydrogen Purge System - CLIIP 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML24019A1682024-01-31031 January 2024 Safety Evaluation Report for Approval of License Termination Plan 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 ML20056E4872020-02-26026 February 2020 Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM) ML19297D6742019-12-0909 December 2019 FCS ISFSI Only Tech Specs SER ML18017B0052018-03-30030 March 2018 Review of the Irradiated Fuel Management Plan (CAC No. MF9553; EPID L-2017-LLL-0009) ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17263B1982017-12-11011 December 2017 Letter and Safety Evaluation, Request for Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17275A2642017-11-21021 November 2017 Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285 ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17144A2462017-06-21021 June 2017 Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16141A7392016-05-27027 May 2016 Safety Evaluation, Review of Aging Management Program of Reactor Vessel Internals Based on MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines ML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval 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 ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval 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 ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval 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 ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building 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) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13141A6082013-06-25025 June 2013 Safety Assessment in Response to Request for Information Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML13017A4672013-01-31031 January 2013 Approval of Request for Change to the Reactor Vessel Surveillance Capsule Removal Schedule ML12333A1192012-12-31031 December 2012 Issuance of Amendment No. 269, Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6) ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1122702902011-08-18018 August 2011 Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e 2024-01-31
[Table view] |
Text
January 16, 2003 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION NO. 1 - ISSUANCE OF AMENDMENT RE: RELOCATION OF NUCLEAR DETECTOR COOLING TECHNICAL SPECIFICATION 2.13 TO THE UPDATED SAFETY ANALYSIS REPORT (TAC NO. MB6470)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 214 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1 (FCS). The amendment consists of changes to the technical specifications (TS) in response to your application dated October 8, 2002.
The amendment relocates TS 2.13, "Nuclear Detector Cooling System," and its associated Bases to the FCS Updated Safety Analysis Report.
A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosures:
- 1. Amendment No. 214 to DPR-40
- 2. Safety Evaluation cc w/encls: See next page
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn Mr. Richard P. Clemens ATTN: James R. Curtiss, Esq. Division Manager - Nuclear Assessments 1400 L Street, N.W. Omaha Public Power District Washington, DC 20005-3502 Fort Calhoun Station P.O. Box 550 Chairman Fort Calhoun, Nebraska 68023-0550 Washington County Board of Supervisors Mr. Daniel K. McGhee P.O. Box 466 Bureau of Radiological Health Blair, NE 68008 Iowa Department of Public Health 401 SW 7th Street Mr. John Kramer, Resident Inspector Suite D U.S. Nuclear Regulatory Commission Des Moines, IA 50309 P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P.O. Box 95007 Lincoln, Nebraska 68509-5007 Mr. David J. Bannister Manager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John B. Herman Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550
ML030220143 NRR-058 OFFICE PDIV-2/PM PDIV-2/PM PDIV-2/LA OGC - NLO RPRP/SC PDIV-2/SC NAME AWang:sab BBenney EPeyton AFernandez RDennig SDembek DATE 12/20/02 12/20/02 12/19/02 1/9/03 12/30/2002 1/13/03 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML030220143.wpd OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 License No. DPR-40
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Omaha Public Power District (the licensee) dated October 8, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance. Implementation includes the incorporation of the changes to the Fort Calhoun Station Updated Safety Analysis Report as described in the licensees application dated October 8, 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 16, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 214 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Replace the following page of Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
REMOVE INSERT 2-60 2-60
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 214 TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By application dated October 8, 2002, Omaha Public Power District (the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. DPR-40) for the Fort Calhoun Station, Unit No. 1 (FCS). The amendment would relocate Technical Specification (TS) 2.13, "Nuclear Detector Cooling System," and its associated Bases in their entirety to the FCS Updated Safety Analysis Report (USAR).
2.0 REGULATORY EVALUATION
In Section 50.36, "Technical Specifications," to Title 10 of the Code of Federal Regulations (10 CFR), the Commission established its regulatory requirements related to the content of TSs. In doing so, the Commission placed emphasis on those matters related to the prevention of accidents and mitigation of accident consequences. The Commission noted that applicants were expected to incorporate into their TSs "those items that are directly related to maintaining the integrity of the physical barriers designed to contain radioactivity." (Statement of Consideration, "Technical Specification for Facility Licenses; Safety Analysis Reports,"
33 FR 18610 (December 17, 1968)). Pursuant to 10 CFR 50.36, TSs are required to include items in the following five categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. However, the rule does not specify the particular requirements to be included in a plants TSs.
On July 22, 1993, the Commission issued its Final Policy Statement, expressing the view that satisfying the guidance in the policy statement also satisfies Section 182a of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.36 (58 FR 39132). The Final Policy Statement gave guidance for evaluating the required scope of the TSs and defined the guidance criteria to be used in determining which of the LCOs and associated surveillances should remain in the TSs.
The Final Policy Statement established four criteria to define the scope of equipment and parameters to be included in the TSs. These criteria were developed for licenses authorizing operation and focused on instrumentation to detect degradation of the reactor coolant system pressure boundary and on equipment or process variables that affect the integrity of fission product barriers during design basis accidents or transients. The fourth criterion refers to the use of operating experience and probabilistic risk assessment to identify and include in the TS,
structures, systems, and components shown to be significant to public health and safety.
Nevertheless, these criteria, codified by 10 CFR 50.36, are the source of the TS requirements for facilities licensed under 10 CFR Part 50. A general discussion of these considerations is provided below.
The regulations contained in 10 CFR 50.36, "Technical Specifications," require that LCOs must be established for each item meeting one or more of the following criteria:
(1) Criteria 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
(2) Criteria 2. A process variable, design feature, or operating restriction that is an initial condition of design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
(3) Criteria 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient and either assumes the failure of or presents a challenge to the integrity of the fission product barrier.
(4) Criteria 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
If a system, structure, or component does not meet any of the above criteria, it need not be included in the TSs.
3.0 TECHNICAL EVALUATION
The licensee has proposed a change to delete TS 2.13 and its Bases and relocate it to the FCS USAR. The nuclear detector cooling system is used to cool the air in the annulus between the reactor vessel and the biological shield. This cooling assures that the concrete in the biological shield does not overheat. Overheating could cause a reduction in concrete strength through a loss of moisture. TS 2.13 currently requires that the annulus exit temperature from the nuclear detector cooling system not exceed a temperature that correlates to 150EF concrete temperature.
Below is the licensees evaluation of this system against the screening criteria of 10 CFR 50.36(c)(2)(ii):
Criterion 1 The nuclear detector cooling system is not an instrumentation system that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
Criterion 2 The nuclear detector cooling system is not a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or challenge to the integrity of a fission product barrier.
Criterion 3 The nuclear detector cooling system is not a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 4 The FCS Probabilistic Safety Assessment does not address the nuclear detector cooling system. This system is considered to be a non-risk contributor to the core damage frequency and offsite releases.
The staff agrees with the licensee that the nuclear detector cooling system does not meet the criteria set forth in 10 CFR 50.36(c)(2)(ii) for inclusion in the TS. Since the nuclear detector cooling system requirements are not required to be in the TS to provide adequate protection of the public health and safety, the staff concludes that the nuclear detector cooling system requirements may be relocated to a licensee-controlled document. Any changes to the FCS USAR are controlled by the provisions of 10 CFR 50.59 and would require staff review and approval if the change did not meet the criteria set forth in 10 CFR 50.59. As TS 2.13 and its associated Bases will be relocated to the FCS USAR, the USAR will continue to assure that the biological shield structure concrete temperature will be maintained below 150EF and therefore, the deletion of TS 2.13 is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Nebraska State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (67 FR 68741).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Brian Benney Date: January 16, 2003