Letter Sequence Other |
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Results
Other: LIC-03-0164, Response to a RAI on Measurement Uncertainty Recapture Power Uprate, LIC-04-0006, Closure of NRC Tack Issues for Fort Calhoun Station Unit No. 1, LIC-04-0061, Notification of Technical Issues Associated with License Amendment No. 225, ML032870394, ML040210313, ML040400333, ML040490383, ML041060362, ML041310501, ML041390246, ML043370117, ML050530011, ML050600428, ML050610222, ML050750059
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MONTHYEARLIC-03-0067, Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power Uprate2003-07-18018 July 2003 Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power Uprate Project stage: Request ML0328703942003-10-14014 October 2003 Withholding from Public Disclosure, Calculation Number FC-6896-P, Secondary Calorimetric Uncertainty Analysis Project stage: Other ML0328705202003-10-14014 October 2003 RAI, Measurement Uncertainty Recapture Power Uprate Project stage: RAI LIC-03-0148, Response to Request for Additional Information - Measurement Uncertainty Recapture Power Uprate2003-10-31031 October 2003 Response to Request for Additional Information - Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LIC-03-0164, Response to a RAI on Measurement Uncertainty Recapture Power Uprate2003-12-15015 December 2003 Response to a RAI on Measurement Uncertainty Recapture Power Uprate Project stage: Other LIC-03-0166, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate2003-12-22022 December 2003 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML0402007572004-01-16016 January 2004 Issuance of License Amendment 224 Revising the Renewed Operating License and the TSs to Increase the Licensed Rated Power by 1.6 Percent from 1500 Megawatts Thermal (Mwt) to 1524 Mwt Project stage: Approval ML0402103132004-01-16016 January 2004 Tech Spec Pages for Amendment 224 Revising the Renewed Operating License and the TSs to Increase the Licensed Rated Power by 1.6 Percent from 1500 Megawatts Thermal (Mwt) to 1524 Mwt Project stage: Other ML0404003332004-02-0909 February 2004 Fort Calhoun Station, Unit 1 - Public Notice of Application for Amendment to Facility Operating License Project stage: Other ML0404903832004-02-13013 February 2004 Amendment, Changes Implementation Date from 30 Days to 120 Days for Amendment No. 224 Issued on 01/16/2004 That Approved Measurement Uncertainty Uprate to Increase Licensed Rated Power by 1.6 Percent from 1500 Megawatts Thermal to 1524 Project stage: Other ML0405803462004-02-18018 February 2004 RAI, License Amendment Request Administrative TS Changes (Tac. MC1535) Project stage: RAI ML0410603622004-04-14014 April 2004 Memo to File, E-mail Regarding Fort Calhoun Emergency Diesel Generating Starting Air System Project stage: Other LIC-04-0061, Notification of Technical Issues Associated with License Amendment No. 2252004-05-0505 May 2004 Notification of Technical Issues Associated with License Amendment No. 225 Project stage: Other ML0413105012004-05-10010 May 2004 5/10/04, Fort Calhoun, Unit 1 - Public Notice of Application for Amendment to Facility Operating License Project stage: Other ML0413901262004-05-14014 May 2004 5/14/04, Fort Calhoun, Unit 1 - TS - Issuance of Amendment Project stage: Approval ML0413902462004-05-14014 May 2004 License Amendment, Amendment Restores Licensed Thermal Power from 1524 Mega Thermal Project stage: Other LIC-04-0073, Response to Request for Additional Information Regarding License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generator Lubricating Oil, & Diesel Generator Starting Air Requirements2004-07-0202 July 2004 Response to Request for Additional Information Regarding License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generator Lubricating Oil, & Diesel Generator Starting Air Requirements Project stage: Response to RAI ML0421202032004-07-23023 July 2004 Tech Spec Pages for Amendment 228 Various Administrative and Editorial Changes Project stage: Acceptance Review ML0421104112004-07-23023 July 2004 Issuance of License Amendment 228 Various Administrative and Editorial Changes Project stage: Approval ML0424300272004-08-27027 August 2004 RAI, Modify Technical Specification 2.3.(4) Project stage: RAI ML0430205742004-10-21021 October 2004 Issuance of License Amendment No. 229, Changing TS 2.7, TS Table 3-5 and TS 5.0 to Modify Requirements for the Diesel Generator Fuel Oil for Consistency with Improved Standard TS Project stage: Approval ML0433501352004-10-21021 October 2004 Tech Spec Pages for Amendment No. 229, Changing TS 2.7, TS Table 3-5 and TS 5.0 to Modify Requirements for the Diesel Generator Fuel Oil for Consistency with Improved Standard TS Project stage: Acceptance Review LIC-04-0102, Request for Additional Information (RAI) Regarding License Amendment Request (Lar), Trisodium Phosphate (TSP) Dodecahydrate Volume.2004-10-29029 October 2004 Request for Additional Information (RAI) Regarding License Amendment Request (Lar), Trisodium Phosphate (TSP) Dodecahydrate Volume. Project stage: Request ML0432705302004-11-0808 November 2004 Issuance of License Amendment No. 230 Relocating Requirements of TS 3.3(1)a and Other Components Subject to ASME XI Boiler & Pressure Vessel Code Inspection and Testing Surveillance and TS 3.4 to Update UFSAR Project stage: Approval ML0433701172004-11-0808 November 2004 TS Pages for Amendment No. 230 Relocating Requirements of TS 3.3(1)a and Other Components Subject to ASME XI Boiler & Pressure Vessel Code Inspection and Testing Surveillance and TS 3.4 to Update UFSAR Project stage: Other LIC-04-0133, Response to NRC RAI on Trisodium Phosphate (TSP) License Amendment Request2004-12-16016 December 2004 Response to NRC RAI on Trisodium Phosphate (TSP) License Amendment Request Project stage: Response to RAI ML0505300112005-02-18018 February 2005 Tech Spec Page for Amendment 231 Elimination of Requirements to Provide Monthly Operating/Annual Occupational Radiation Exposure Reports Project stage: Other ML0505500612005-02-18018 February 2005 Issuance of License Amendment 231 Elimination of Requirements to Provide Monthly Operating/Annual Occupational Radiation Exposure Reports Project stage: Approval ML0506004282005-03-0101 March 2005 Amendment, Revision of TS Section 2.3(4) & TS Section 3.6(2)d.(i) Project stage: Other ML0506102222005-03-0101 March 2005 Technical Specifications, Revision of TS Section 2.3(4) & TS Section 3.6(2)d.(i) Project stage: Other ML0507500592005-03-11011 March 2005 Tech Spec Pages for Amendment 233 Revising TS 5.9.5 to Be Consistent with Specification 5.6.5 of NUREG-1432 Project stage: Other ML0507505342005-03-11011 March 2005 Issuance of License Amendment 233 Revising TS 5.9.5 to Be Consistent with Specification 5.6.5 of NUREG-1432 Project stage: Approval LIC-04-0006, Closure of NRC Tack Issues for Fort Calhoun Station Unit No. 12005-07-0101 July 2005 Closure of NRC Tack Issues for Fort Calhoun Station Unit No. 1 Project stage: Other 2004-02-18
[Table View] |
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Category:Letter
MONTHYEARML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 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 ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request 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 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 IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 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 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, 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 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, 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 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, 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 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 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 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 2024-07-08
[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
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March 1, 2005 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: (TAC NO. MC3214)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 232 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated May 21, 2004, as supplemented on October 29, and December 16, 2004.
The amendment revises TS Section 2.3(4), "Emergency Core Cooling System - Trisodium Phosphate (TSP)," regarding the volume and form of the TSP and TS Section 3.6(2)d.(i),
"Safety Injection and Containment Cooling Systems Tests," regarding the surveillance requirement for the TSP volume.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next 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. 232 to DPR-40
- 2. Safety Evaluation cc w/encls: See next page
March 1, 2005 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: (TAC NO. MC3214)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 232 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated May 21, 2004, as supplemented on October 29, and December 16, 2004.
The amendment revises TS Section 2.3(4), "Emergency Core Cooling System - Trisodium Phosphate (TSP)," regarding the volume and form of the TSP and TS Section 3.6(2)d.(i),
"Safety Injection and Containment Cooling Systems Tests," regarding the surveillance requirement for the TSP volume.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next 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 DISTRIBUTION:
PUBLIC GHill (2)
Enclosures:
- 1. Amendment No. 232 to DPR-40 PDIV-2 Reading
- 2. Safety Evaluation RidsNrrDlpmPdiv (HBerkow)
RidsNrrPMAWang cc w/encls: See next page RidsNrrLALFeizollahi RidsOgcRp RidsACRSACNWMailCenter RidsRegion4MailCenter(M. Hay)
TBoyce TS: ML050610222 NRR-100 RidsNrrDlpmPdiv2 (RGramm)
ACCESSION NO.: ML050600428 PKG.: ML050600431 NRR-058 OFFICE PDIV-2/PM PDIV-2/LA EMCB: DE OGC Nlo PDIV-2/SC NAME AWang:sp LFeizollahi:lxf1 LLund APH RGramm DATE 2/24/05 2/24/05 2/23/05 2/25/05 3/1/05 DOCUMENT NAME: E:\Filenet\ML050600428.wpd w/comments OFFICIAL RECORD COPY
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No.232 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 May 21, 2004, as supplemented on October 29, and December 16, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, Renewed 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. 232, 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert A. Gramm, 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: March 1, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 232 RENEWED FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT TOC - Page 8 TOC - Page 8 2.3 - Page 4 2.3 - Page 4 2.3 - Page 6 2.3 - Page 6
2.3 - Page 8 3.6 - Page 2 3.6 - Page 2 3.6 - Page 6 3.6 - Page 6
3.6 - Page 7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 232 TO RENEWED 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 May 21, 2004 (ML041470121), as supplemented on October 29, 2004 (ML043030426), and December 16, 2004 (ML043520417), Omaha Public Power District (OPPD/the licensee) requested changes to the Technical Specifications (Appendix A to Renewed Facility Operating License No. DPR-40) for the Fort Calhoun Station, Unit No. 1 (FCS).
The amendment revises Technical Specifications (TS) Section 2.3(4), "Emergency Core Cooling System - Trisodium Phosphate (TSP)," and TS Section 3.6(2)d.(i), "Safety Injection and Containment Cooling Systems Tests." Specifically, the licensees proposed changes consist of deleting the requirement that the trisodium phosphate (TSP) be of the "dodecahydrate" form and instead specifying that hydrated TSP (45-57 percent moisture content) is required. In addition, instead of having a fixed volume of TSP required, the licensee proposed a new methodology in which the volume of TSP required will vary throughout the operating cycle as determined by a new TS Figure 2-3.
The additional information provided in the supplemental letters dated October 29, 2004 and December 16, 2004, did not expand the scope of the application as noticed and did not change the Nulear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination published in the Federal Register on June 8, 2004 (69 FR 32075).
2.0 REGULATORY EVALUATION
OPPD has applied for a license amendment to its TSs 2.3(4) and 3.6 under 10 CFR 50.90. The changes are consistent with the applicable regulatory recommendations in NUREG 0800, Section 6.5.2, "Containment Spray as a Fission Product Cleanup System." Subsection II.1.g specifies that the pH of all solutions in the containment sump and all additives for reactivity control, fission product removal, or other purposes (boric acid) should be maintained at a level high enough to assure that significant long-term iodine re-evolution does not occur. Long-term iodine retention may be assumed only when the equilibrium sump solution pH, after mixing with the primary coolant and emergency core cooling system injection sources, is above 7.0.
The FCS was licensed in accordance with the 70 draft General Design Criteria (GDC) published for comment in the Federal Register (32 FR 10213) on July 11, 1967. The 70 draft GDC are
contained in Appendix G of the FCS Updated Safety Analysis Report. The acceptance criteria for the fission product cleanup function of the containment spray system are based on meeting the relevant requirements of the following regulations:
Draft GDC 42, "Engineered Safety Features Components Capability," as it relates to containment atmosphere cleanup systems being designed to control fission product releases to the reactor containment following postulated accidents.
Draft GDC 62, "Inspection of Air Clean-up Systems," as it relates to containment atmosphere cleanup systems being designed to permit periodic inspections.
Draft GDC 64, "Testing of Air Clean-up Systems," as it relates to containment atmosphere cleanup systems being designed for appropriate periodic functional testing.
The proposed amendment is in compliance with the draft GDCs.
OPPD has stated that the technical analysis and risk information provided in its submittal satisfies all regulatory requirements and guidance concerning the type and volume of active TSP required in the containment sump to ensure post loss-of-coolant accident (LOCA) recirculation water maintains a pH greater than or equal to 7.0 but less than or equal to 7.5.
Increasing the pH greater than 7.5 would negatively impact equipment environmental qualification (EEQ) as required by 10 CFR 50.49 and hydrogen generation design basis assumptions by making the containment sump too basic.
3.0 TECHNICAL EVALUATION
The license amendment for the FCS consists of deleting the requirement that the TSP be of the dodecahydrate form and instead requiring a hydrated TSP (45-57 percent moisture content).
This change will make TS 2.3(4) consistent with NUREG-1432, Revision 2, "Standard Technical Specifications Combustion Engineering Plants," which does not require a specific type of TSP.
In addition, the licensee proposes that instead of having a fixed volume requirement of TSP provided in the TSs, a new figure (2-3) will be added to its TSs that provides a required volume of TSP that changes as the critical boron concentration gradually decreases. The surveillance requirement of TS 3.6(2).d.(i) is revised to require a volume of TSP that is within the area of acceptable operation of TS Figure 2-3. The purpose of this amendment is to prevent the licensee from entering a Limiting Condition for Operation caused by the effects of densification at some future time.
A variety of acids and bases are produced in containment after a LOCA. The pH value of the containment sump water will depend on the concentration of the chemical species dissolved in it and on the buffering action of TSP. There are two considerations for determining the pH of the containment sump after a LOCA. In order to prevent release of elemental iodine to the containment atmosphere after a LOCA, the sump pH must be maintained greater than or equal to 7.0. In addition, for EEQ considerations the pH must be maintained less than or equal to 7.5.
The TSP baskets have a maximum capacity of 131.9 ft3, which will provide the correct pH for the containment sump after a LOCA.
After a LOCA, the containment sump is mostly filled with water coming from the systems containing boric acid: safety injection refueling water tank (SIRWT), safety injection tanks (SITs), boric acid storage tanks (BASTs) and the reactor coolant system (RCS). As the water starts accumulating in containment, the water itself dissolves the TSP contained in the baskets.
Mixing is achieved as the solution is continuously recirculated. The TSP acts as a buffer to maintain the sump pH greater than or equal to 7.0 and less than or equal to 7.5. Maintaining sump water in an alkaline condition is needed for preventing dissolved radioactive iodine from being released to the containment atmosphere during the recirculation containment spray injection. In addition, keeping the sump pH at or above 7.0 will help reduce stress corrosion cracking of austenitic stainless steel components in containment. Most of the iodine leaves the damaged core in an ionic form which is readily dissolved in the sump water. However, in an acidic environment, some of it becomes converted into an elemental form which is much less soluble, causing re-evolution of iodine to the containment atmosphere.
The minimum required amount of TSP is a function of different factors: (1) cycle specific hot zero power critical boron concentration (HZP CBC); (2) boron concentrations, maximum volumes and temperatures of the RCS, SIRWT, SITs and BASTs; and (3) the acids generated from the degradation of electrical cable jackets and the irradiation of water and air in the containment. Future fuel and core designs are expected to increase the RCS HZP CBC at the beginning of cycle (BOC). The current licensees TSs require a minimum active TSP volume of
$126 ft3, which represents the densified amount of TSP in the baskets. The storage baskets have a maximum capacity of 131.9 ft3. Because of the increase in the HZP CBC, an increase in the TSP volume at the BOC would be required to maintain a pH $7.0. Currently, the licensee fills up the baskets to their maximum capacity at the BOC to compensate for the effects of densification (because of the high humidity existing in the containment, the TSP tends to agglomerate, thereby causing the volume to decrease and the density to increase, although the mass remains the same). Licensee test results have shown that densification can account for a 5 percent loss of the volume of TSP over the operating cycle. Raising the minimum TSP requirement for the entire cycle would reduce the margin (volume of TSP above that required by TSs) between the maximum capacity of the baskets and the minimum TSP volume required by TSs. This reduction could result in the volume of TSP at the end of cycle (EOC) not to be in compliance with the TSs.
In order to prevent this from happening, the licensee considered increasing the amount of TSP in containment by adding an additional basket. Even though this solution would work at the BOC when the HZP CBC was significantly higher, this could result in a pH greater than 7.5 at the EOC when HZP CBC was significantly lower. This would negatively impact EEQ and hydrogen generation design basis assumptions by making the containment sump too basic.
This option was rejected by the licensee.
Another option analyzed by the licensee consisted in, rather than having a required fixed volume of TSP, use of a new figure (2-3) will allow the required TS volume of TSP to change as the critical boron concentration gradually decreases throughout the operating cycle. Having the required volume of TSP trending downward during the operating cycle with decreasing HZP CBC will provide an adequate margin to account for densification and will help maintain the sump pH between 7.0 and 7.5. This option doesnt imply that the existent TSP volume will actually decrease throughout the operating cycle. In a letter dated August 27, 2004 (ML042430027), the staff asked the licensee to clarify if other mechanisms causing loss of TSP
besides densification existed and how were these incorporated in the process of construction of the graph in Figure 2-3. By letter dated October 29, 2004, the licensee responded that no credible material loss mechanisms have been identified other than densification. Therefore, only a reduction of 5 percent in the volume of TSP is expected at the EOC.
Even though there is a loss of volume due to densification, the TSP mass remains the same throughout the operating cycle. If there is no mass loss of the TSP, the amount of TSP corresponding to 131.9 ft3 would produce a low pH value at the BOC when boric acid concentration is high and a high pH value at the EOC when boric acid concentration is low. In a letter dated August 27, 2004, the staff asked the licensee to clarify if a high pH value at the EOC would have a negative impact on the EEQ. By letter dated October 29, 2004, the licensee responded that the EEQ is maintained with the current mass equivalent amount of TSP in containment. Furthermore, in a letter dated December 16, 2004, the licensee indicated that an upper limit of 135.71 ft3 is the total effective volume of TSP allowed in the baskets. The total effective TSP volume, as defined by the licensee, is the cumulative volume of the TSP initially placed into the baskets and the volume of TSP added to top-off the baskets (due to the densification) during subsequent refueling outages. The licensee keeps records of the cumulative volume of TSP added to the baskets from cycle to cycle in order to prevent exceeding the total effective volume. This limit will ensure that EEQ requirements are maintained by assuring that containment sump pH does not exceed 7.5 should a LOCA occur at the end of cycle. The licensees compliance with the proposed figure should ensure that the containment sump pH stays greater than or equal to 7.0 but less than or equal to 7.5 to meet EEQ and hydrogen generation design basis objectives.
The licensee also proposes to delete the TS requirement that the TSP be of the dodecahydrate form and instead specify that hydrated TSP, with a moisture content of 45-57 percent is required. The licensee will incorporate information from the Basis of 3.5.5 of NUREG-1432, Revision 2, by stating: "The hydrated form (45-57 percent moisture) of TSP is used because of the high humidity in the containment building during normal operation. Since the TSP is hydrated, it is less likely to absorb large amounts of water from the humid atmosphere and will undergo less physical and chemical change than the anhydrous form of TSP." In a letter dated July 8, 2004 (ML041950091), the staff asked the licensee whether hydrated forms of TSP have different densities and, if any difference exists, to provide the value used in its calculations. In a letter dated October 29, 2004, the licensee responded that the most limiting combination of parameters as specified in the procurement specifications have been used in its calculation, thus adding more conservatism to the calculation.
After an accident, the pH of the containment sump water depends on the amounts of acidic and basic chemical materials either released from the damaged core or generated in containment and subsequently dissolved in the sump water. If the pH falls below 7, radioactive iodine could be released to the containment atmosphere. The addition of a buffering solution will keep the water pH at or above 7, therefore preventing the iodine from being released. The licensee uses TSP held in baskets throughout the containment as a pH buffer. The licensees proposed amendment stating that the TSP requirement be in a downward trend as the HZP CBC decreases will still ensure that at any time during the operating cycle the TSP present in the baskets will help prevent the sump water pH from falling below 7. The only anticipated decrease of the volume of TSP in the baskets is due to densification, which is already accounted for in the licensees calculations, but the mass is expected to remain the same throughout the operating cycle, thus ensuring the sump pH will remain at or above 7 throughout the duration of the accident.
Based on the above, the staff concludes that proposed TS changes are acceptable.
OPPD has revised Bases Sections 2.3 and 3.6 to reflect the new TS requirements. The staff has reviewed these Bases changes and has no objections to them.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a 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 (69 FR 32075). 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 amendment.
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 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.
Principal Contributor: Y. Diaz-Castillo Date: March 1, 2005
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn Mr. Daniel K. McGhee ATTN: James R. Curtiss, Esq. Bureau of Radiological Health 1400 L Street, N.W. Iowa Department of Public Health Washington, DC 20005-3502 401 SW 7th Street, Suite D Des Moines, IA 50309 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Centential Mall, South P.O. Box 95007 Lincoln, NE 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