Letter Sequence Approval |
---|
|
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
|
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] |
|
---|
Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 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 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 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 Commissions Analysis of Omaha Public Power Districts 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 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, 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 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 2024-09-18
[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
October 21, 2004 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 (TAC NO. MC1536)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 229 to Renewed 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 December 1, 2003, as supplemented by letter dated July 2, 2004.
The amendment changes TS 2.7, "Electrical Systems, TS Table 3-5, "Minimum Frequencies for Equipment Tests," and TS 5.0, "Administrative Controls," to modify the requirements for the diesel generator (DG) fuel oil for consistency with the Improved Standard Technical Specifications. The amendment also adds requirements for the DG lubricating oil and DG starting air.
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. 229 to DPR-40
- 2. Safety Evaluation cc w/encls: See next page
October 21, 2004 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 (TAC NO. MC1536)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 229 to Renewed 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 December 1, 2003, as supplemented by letter dated July 2, 2004.
The amendment changes TS 2.7, "Electrical Systems, TS Table 3-5, "Minimum Frequencies for Equipment Tests," and TS 5.0, "Administrative Controls," to modify the requirements for the diesel generator (DG) fuel oil for consistency with the Improved Standard Technical Specifications. The amendment also adds requirements for the DG lubricating oil and DG starting air.
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. 229 to DPR-40 PDIV-2 Reading LLund
- 2. Safety Evaluation RidsNrrDlpmPdiv (HBerkow) JYerokun RidsNrrPMAWang DThatcher cc w/encls: See next page RidsNrrLAEPeyton RidsOgcRp RidsAcrsAcnwMailCenter RidsRegion4MailCenter (C. Johnson)
- SE Dated TBoyce RidsNrrDlpmPdiv2 (RGramm)
ACCESSION NO.: ML OFFICE PDIV-2/PM PDIV-2/LA IROB:Sec A SPLB* EMCB*
NAME AWang:mp EPeyton TBoyce JYerokun LLund DATE 10/18/04 10/18/04 9/29/04 6/15/04 7/29/04 OFFICE OGC IROB/SC PDIV-2/SC NAME MHiggins DThatcher RGramm DATE 10/12/04 10/18/2004 10/18/04 OFFICIAL RECORD COPY
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 Mr. Richard P. Clemens P.O. Box 466 Division Manager - Nuclear Assessments Blair, NE 68008 Omaha Public Power District Fort Calhoun Station Mr. John Kramer, Resident Inspector P.O. Box 550 U.S. Nuclear Regulatory Commission Fort Calhoun, NE 68023-0550 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 Cententiall 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
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 229 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 December 1, 2003, as supplemented by letter dated July 2, 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. 229, 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 from the date of its 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: October 21, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 229 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 2.7 - Page 1 2.7 - Page 1 2.7 - Page 3 2.7 - Page 3 2.7 - Page 4 2.7 - Page 4 2.7 - Page 5 2.7 - Page 5 2.7 - Page 6 2.7 - Page 6
2.7 - Page 7
2.7 - Page 8 3.2 - Page 3 3.2 - Page 3
3.2 - Page 3a
3.2 - Page 3b 3.2 - Page 6 3.2 - Page 6 3.2 - Page 7 3.2 - Page 7 3.2 - Page 8 3.2 - Page 8 3.2 - Page 9 3.2 - Page 9 5.0 - Page 19 5.0 - Page 19
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 229 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 December 1, 2003 (ML033380968), as supplemented by letter dated July 2, 2004 (ML041890312), Omaha Public Power District (OPPD) requested changes to the Technical Specifications (TS) (Appendix A to Renewed Facility Operating License No. DPR-40) for the Fort Calhoun Station, Unit No. 1 (FCS).
The proposed amendment would revise TS 2.7, "Electrical Systems," TS Table 3-5, "Minimum Frequencies for Equipment Tests," and TS 5.0, "Administrative Controls." Specifically, the proposed changes would revise the requirements for diesel generator (DG) fuel oil for consistency with the Improved Standard Technical Specifications (ISTS) and adds requirements for the DG lubricating oil and DG starting air.
The additional information provided in the supplemental letter dated July 2, 2004, did not expand the scope of the application as noticed and did not change the NRC staff's original proposed no significant hazards consideration determination published in the Federal Register on February 17, 2004 (69 FR 7526).
2.0 REGULATORY EVALUATION
If both sources of normal auxiliary power are lost (unit auxiliary transformer and system auxiliary transformer), the equipment essential to safe shutdown will be supplied by the seismic Class I DGs. The DGs are designed to furnish reliable in-plant alternating current (AC) power adequate for safe shutdown and for operation of engineered safeguards equipment. For adequate reliability, two DGs are provided. Each DG is complete with all auxiliaries necessary for operation and for ensuring quick starts. These DGs will automatically start and tie onto the 4160 volt AC vital buses on a loss of voltage on the bus.
The requested changes modify requirements for DG fuel oil for consistency with the ISTS and adds requirements for DG lubricating oil and DG starting air. As stated in the TS Bases, stored diesel fuel oil is required to have inventory to support seven days of full load operation. A seven-day supply of lubrication oil must also be available. This quantity is promulgated by
American National Standard ANSI N195-1976, "Fuel Oil Systems for Standby Diesel Generators" as endorsed by NRC Regulatory Guide (RG) 1.137 of same title. Fuel oil is also required to meet specific standards of quality. The fuel oil properties governed by the surveillance requirements (SRs) are water and sediment content, kinematic viscosity, specific gravity (or API gravity), and impurity level. The recommended fuel oil surveillance practices are addressed in RG 1.137. The basis for the starting air requirement is General Design Criterion 17, "Electric power systems," as related to the capability of the DG air starting system to meet independence and redundancy criteria. The industry standard that has been adopted to address this is that the air starting system should be capable of five cold start attempts without recharging the receiver(s).
The proposed TS amendment changes the surveillance interval for checking emergency diesel generator (EDG) fuel oil inventory and fuel oil water and sediment content. These changes affect SR 3.2, "Equipment and Sampling Tests." In addition, the licensee proposes additions to Limiting Conditions for Operation (LCO) Section 2.7, "Electrical Systems." The additions to the LCOs clarify the scope, allowed outage times, and actions required regarding EDG lubricating oil inventory, EDG fuel oil inventory, stored EDG fuel oil quality, and new EDG fuel oil quality.
The proposed TS changes also add a diesel fuel oil testing program to TS 5.0, "Administrative Controls." This program is intended to ensure that fuel oil is sampled and analyzed as a preventative measure against EDG degradation. The diesel fuel oil testing program references specific ASTM standards (ASTM D-2276 Method A-2 or A-3). The licensee proposes to move any references to specific standards to a licensee-controlled document to allow flexibility in the testing methods used. The licensee acknowledges that changes to the licensee-controlled document are performed in accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59.
The minimum design requirements for Fort Calhoun are based upon plant-specific design criterion documented in Appendix G of the FCS Updated Safety Analysis Report. The changes to TS 2.7, 3.2, and 5.0 satisfy the FCS Design Criterion 24, "Emergency Power Protection Systems," and FCS Design Criterion 39, "Emergency Power for Engineered Safety Features,"
which are similar to GDC 17.
The basis the staff used to determine if the proposed changes are acceptable is conformance to the existing regulatory basis and the precedents that have been established by License Amendment Nos. 227 and 201 to Facility Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2, respectively, and License Amendment No.
180 to Facility Operating License No. DPR-20 for the Palisades Plant. These license amendments converted the Calvert Cliffs and Palisades technical specifications to standard technical specification (STS) format consistent with the provisions of NUREG-1432, Revision 1, "Standard Technical Specifications, Combustion Engineering Plants" dated April 1995.
Consistency with the provisions of NUREG-1432 is considered to be sufficient basis for accepting proposed TS changes for Fort Calhoun where plant-specific considerations are judged to be commensurate with the basis of the corresponding NUREG-1432 requirement.
3.0 TECHNICAL EVALUATION
The staff has reviewed the licensee's regulatory and technical analyses in support of its proposed license amendment which are described in Sections 5.0 and 6.0 of the licensee's submittal. The detailed evaluation below will support the conclusion 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.
3.1 Proposed New LCO 2.7(1)n New LCO 2.7(1)n states, "Lubricating oil inventory for each DG is $ 500 gallons." This TS is being added under the current LCO 2.7(1), "Minimum Requirements." The licensee stated that this proposed change will assure that a seven-day supply of DG lubricating oil is maintained.
This requirement is more restrictive since no minimum requirement for the quantity of lubricating oil previously existed. Maintaining a seven-day supply is an industry standard and is consistent with LCO 3.8.3, "Diesel Fuel Oil, Lube Oil, and Starting Air," of NUREG-1432 and with the precedent set by License Amendment No. 180 for the Palisades Plant. Therefore, the staff finds the addition of this new requirement to be acceptable.
3.2 Proposed New LCO 2.7(1)o New LCO 2.7(1)o states, "Each required starting air receiver bank pressure is $ 190 psig." This TS is being added under current LCO 2.7(1), "Minimum Requirements." The licensee stated that this proposed change will assure that sufficient starting air is available for five successive DG start attempts without recharging the air receivers. Maintaining sufficient starting air pressure for five successive cold start attempts without recharging the receiver(s) is an industry standard. This requirement is more restrictive since no minimum TS requirement for starting air receiver bank pressure previously existed. Specifying a required starting air receiver pressure is consistent with LCO 3.8.3, "Diesel Fuel Oil, Lube Oil, and Starting Air," of NUREG-1432 and with SRP Section 9.5.6, "Emergency Diesel Engine Starting System." It is also consistent with the precedent set by License Amendment No. 180 for the Palisades Plant. Therefore, the staff finds the addition of this new requirement to be acceptable.
3.3 Proposed New LCO 2.7(3)
Proposed LCO 2.7(3), "Modification on Minimum Requirements for Diesel Fuel Oil, Diesel Lube Oil, and Starting Air," is being added under current LCO 2.7, "Electrical Systems." This LCO permits several conditions, i.e., modifications to minimum requirements, to exist simultaneously with the reactor coolant above 300EF as long as the reactor remains subcritical. This applicability statement is equivalent to that in the ISTS. The statement in proposed LCO 2.7(3),
"any of the following conditions will be allowed" is consistent with that presented in tabular format in LCO 3.8.3 of NUREG-1432 along with the Note in LCO 3.8.3 stating, "Separate Condition entry is allowed for each DG." The current TS only permits one modification to minimum requirements to exist at a given time. The proposed LCO 2.7(3) is presented here, for clarity, in its entirety. The proposed LCO 2.7(3) reads as follows:
(3) Modification on Minimum Requirements for Diesel Fuel Oil, Diesel Lube Oil, and Starting Air.
The minimum requirements may be modified to the extent that any of the following conditions will be allowed after the reactor coolant has been heated above 300º F. However, the reactor shall not be made critical unless all minimum requirements are met.
- a. If the inventory of diesel fuel oil in FO-1 is less than 16,000 gallons and/or FO-10 is less than 10,000 gallons, but the combined inventory in FO-1 and FO-10 is greater than a 6 day supply (23,350 gallons), then restore the required inventory within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- b. If one or more diesel generators has lube oil inventory 500 gallons and ' 450 gallons, then restore the lube oil inventory to within limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- c. If the total particulates of fuel oil stored in FO-1 or FO-10 is not within limits, then restore fuel oil total particulates to within limits within 7 days.
- d. If the properties of new fuel oil stored in FO-1 or FO-10 is not within limits, then restore stored fuel oil properties to within limits within 30 days.
- e. If one or more diesel generators has the required starting air receiver bank with pressure 190 psig and ' 150 psig, then restore starting air receiver bank pressure to '190 psig within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- f. If the Required Action and associated Completion Time of a, b, c, d, or e are not met or one or more diesel generators have diesel fuel oil, lube oil, or a required starting air subsystem not within limits for reasons other than a, b, c, d, or e, then declare the associated DG inoperable immediately.
LCO 2.7(3)a allows the "minimum requirement" for DG fuel oil quantity (LCO 2.7(1)m) to be modified to the extent that the listed condition will be allowed after the reactor coolant has been heated above 300EF. This has been added to address actions to restore DG fuel oil. This requirement, which was existing minimum requirement LCO 2.7(2)k, is being placed in this location for consistency with NUREG-1432. In this location, it is permitted along with other conditions. In its previous location it was permitted if it was the only modification to "minimum requirements." This modification is consistent with NUREG-1432 and with the precedents set by License Amendment No. 180 for the Palisades Plant and by License Amendment Nos. 227 and 201 for Calvert Cliffs Units 1 and 2, respectively. The staff finds this modification acceptable.
LCO 2.7(3)b allows the minimum requirement for DG lube oil to be modified to the extent that the listed condition will be allowed after the reactor coolant has been heated above 300EF. This is a new LCO. This condition represents a reduction of the lube oil supply that is below the seven-day supply but above a six-day supply. The licensee stated that this circumstance may be caused by events such as full load operation being required after an inadvertent start while at minimum required level, or feed and bleed operations of the lube oil which may be necessitated by increasing particulate levels or any number of other oil quality degradations.
The licensees cited justification for this requirement is that which is stated in the Bases of NUREG-1432 for this requirement. That is that this restriction allows sufficient time for obtaining the requisite replacement volume. A period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is considered sufficient to complete restoration of the required level prior to declaring the DG inoperable. This period is acceptable based on the remaining capacity ('6days), the fact that procedures will be initiated to obtain replenishment, and the low probability of an event during this brief period. This change is consistent with STS 3.8.3 of NUREG-1432 and with the precedent set by License Amendment No. 180 for the Palisades Plant. This change is more restrictive because the "minimum requirement" (new LCO 2.7(1)n) on lube oil quantity which it modifies did not exist previously. The staff finds this change acceptable.
LCO 2.7(3)c allows up to seven days for restoration of fuel oil particulate concentration to within the required limits. This condition is entered if the EDG fuel oil fails the acceptance criteria. In addition to the possibility that the fuel oil is contaminated, entrance into this condition could be attributed to poor sampling technique, contaminated sampling equipment, or laboratory errors.
The seven-day window is proposed in order to allow time for re-evaluation of the particulate concentration in the fuel oil before declaring the EDG inoperable. Particulate concentration is unlikely to change significantly between surveillance intervals. Therefore, any samples that stray from the trend established by recent samples are potentially the result of a poorly taken sample or an error in analysis. If a sample truly indicates a particulate concentration that exceeds the requirements, the EDG would still be able to perform its intended duty. Fuel oil that exceeds the particulate concentration threshold, while not ideal for prolonged operation, will still burn properly in the diesel engine. The ability of the diesel to operate with elevated particulate concentration, in conjunction with the assurance that proper engine performance has been demonstrated within the prior 31 days, serves as reasonable justification for an allowance that fuel oil particulate levels be restored to a level within the requirements in no more than 7 days. Therefore, the staff finds this change acceptable.
LCO 2.7(3)d allows 30 days to restore the properties of new fuel oil to within the required limits if the fuel oil does not meet the standards of the fuel oil testing program. The fuel oil properties governed by the fuel oil testing program include the water and sediment content, kinematic viscosity, specific gravity (or API gravity), and impurity level. The period of 30 days provides time to test the stored fuel oil to determine that the new fuel oil, when mixed with the previously stored fuel oil, remains acceptable. If an analysis determines that the stored fuel oil is not within requirements, the 30 days would allow time to restore the stored fuel oil properties.
Restoration could include feed and bleed procedures and filtering of the fuel oil. During the period of fuel oil restoration, the EDG would still be capable of performing its intended function if an EDG start and load was required. The requirements of the fuel oil testing program are designed to verify that the fuel oil is of high quality in order to prolong engine life and reduce required maintenance. Therefore, exceeding the requirements of the fuel oil testing program for the relatively short period of time required to restore the fuel oil properties (a maximum of
30 days) will not have an immediate impact on EDG operation. Therefore, the staff finds this change acceptable.
LCO 2.7(3)e allows the minimum requirement for DG starting air to be modified to the extent that the listed condition will be allowed after the reactor coolant has been heated above 300EF.
This is a new requirement. This change is considered more restrictive because the "minimum requirement" (new LCO 2.7(1)o) on starting air which it modifies did not exist previously. FCS has two starting air systems, each capable of five DG starts. The word "required" is used in the new TS to distinguish it from the redundant equipment. This indicates that no action is entered if the redundant equipment becomes inoperable. This TS is consistent with ISTS 3.8.3 of NUREG-1432 and with the precedent set by License Amendment No. 180 for the Palisades Plant in that it sets a minimum requirement on receiver pressure. Therefore, the staff finds this change acceptable.
LCO2.7(3)f is a new requirement. This requirement directs immediate declaration of DG inoperability if the required action and completion times of 2.7(3)a thru e are not met or if one or more DGs have diesel fuel oil, lube oil, or a required starting air subsystem not within limits for any other reason. This requirement is consistent with ISTS 3.8.3 of NUREG-1432 and with the precedents set by License Amendment Nos. 227 and 201 for Calvert Cliffs Units 1 and 2 respectively and License Amendment No. 180 for the Palisades Plant. Therefore, the staff finds this change acceptable.
The proposed changes to TS 2.7 are consistent with NUREG-1432. The staff finds the addition of LCO 2.7(3) and its associated requirements (a, b, c, d, e, and f), the addition of Section 2.7(1)n, and the relocation of Section 2.7(2)k to Section 2.7(3)a acceptable.
3.4 Proposed Surveillance Frequencies The following items are proposed changes and additions to existing Table 3-5, "Minimum Frequencies for Equipment Tests." Item 9a is a modification of an existing requirement and items 9b through 9e are proposed new requirements.
Test Frequency USAR Section 9a. Diesel Fuel Supply Fuel Inventory M 8.4 9b. Diesel Lubricating Oil Lube Oil Inventory M 8.4 Inventory 9c. Diesel Fuel Oil Test Properties In Accordance 8.4 Properties with the Diesel Fuel Oil Testing Program
Test Frequency USAR Section 9d. Required Diesel Air Pressure M 8.4 Generator Air Start Receiver Bank Pressure 9e. Check For and Check For Water Q 8.4 Remove Accumulated And Remove Water From Each Fuel Oil Tank The surveillance interval for the diesel fuel supply surveillance appears as proposed 9a in the table. It is changed from current number 9. The frequency is being changed from daily to monthly. The licensee cited the ISTS Bases as justification for the change. That is, that the surveillance provides verification that there is a seven-day supply of fuel oil, and that the seven-day period is sufficient to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. Also, the 31-day surveillance interval is adequate to ensure that a sufficient supply of fuel oil is available, since unit operators would be aware of any large uses of fuel oil during this period. If a large volume of fuel is used, the operators take action to replenish the fuel oil in order to maintain the required inventory. This change is consistent with NUREG-1432 and with the precedent set by License Amendment Nos. 227 and 201 for Calvert Cliffs Units 1 and 2, respectively. Therefore, the staff finds this acceptable.
Item 9b is a new requirement stating that the diesel lubricating oil inventory is required to be verified within limits on a monthly basis. This is considered more restrictive because this requirement did not exist previously in the TS. The licensee also cited the ISTS Bases as justification for this change. That is, the surveillance provides verification that there is a seven-day supply of lube oil. The 500 gallon requirement (new LCO2.7(1)n) is based on the DG manufacturer consumption values for the run time of the DG. Implicit in this SR is the requirement to assure the capability to transfer the lube oil from its storage location to the DG, since the DG lube oil sump does not hold adequate inventory for seven days of full load operation without the level reaching the manufacturer recommended minimum level. The 31-day surveillance interval is adequate to ensure that a sufficient lube oil supply is onsite, since DG start and run times are closely monitored by the unit staff. This change is consistent with NUREG-1432 and with the precedent set by License Amendment No. 180 for the Palisades Plant. Therefore, the staff finds this basis acceptable.
Surveillance 9c is added to Table 3-5 stating that the diesel fuel oil properties are to be tested in accordance with the diesel fuel oil testing program. This program mandates that tests are performed as a means of determining whether new fuel oil is of an appropriate grade and is not contaminated in any way that may have a detrimental impact on diesel engine combustion.
These tests are to be performed prior to adding the new fuel oil to the storage tanks and must be conducted within 31 days of receiving the new fuel. This surveillance interval is established based on fuel oil degradation trends. Fuel oil degradation resulting from long-term storage manifests in the form of increased particulate concentration. The proposed bases for this surveillance call for the use of ASTM 6217-98 to determine particulate concentration. The
licensee proposes an exception to ASTM 6217-98 in that the filters used for the test may have a nominal pore size of up to 3 microns. This exception to the standard is added because the FCS inline filters are not designed to trap particles smaller than 3 microns. Particles less than 3 microns in size are not known to cause degradation of diesel engine performance, so the staff finds this change, including the exception, to be acceptable.
The FCS quality assurance plan references the guidance of RG 1.137, which recommends that new fuel should be analyzed within two weeks of being added to the supply tanks. Because the proposed SR 9c allows the analysis to be performed within 31 days, the licensee identified this change to the quality assurance program as a reduction in commitment in accordance with the provisions of 10 CFR 50.54(a)(4). The staff has reviewed the change and finds that an adequate basis is established by ISTS Section 3.8.3 and is therefore acceptable. The quality assurance plan should be revised to reflect the acceptability of a 31 day sampling period.
Item 9d is a new requirement stating that the diesel generator air start receiver pressure is required to be verified within limits on a monthly basis. The licensee cited the ISTS Bases as justification for the change. That is, that the surveillance ensures that without the aid of the refill compressor, sufficient air start capacity for each DG is available. The system design requirements provide for a minimum of five engine start cycles without recharging. A start cycle is defined as the cranking time required to accelerate the DG to firing speed. The pressure specified in this SR is intended to reflect the lowest value at which the five starts can be accomplished. The 31-day surveillance interval takes into account the capacity, capability, redundancy, and diversity of the AC sources and other indications available in the control room, including alarms, to alert the operator to below normal air start pressure. This change is consistent with NUREG-1432 and with the precedent set by License Amendment No. 180 for the Palisades Plant. Therefore, the staff finds this acceptable.
A surveillance to check for and remove accumulated water from each fuel oil storage tank has been added as item 9e to Table 3-5. This surveillance is designed to eliminate the potential for water entrainment in the fuel oil during EDG operation and to eliminate an environment that might result in microbiological fouling. Based on plant-specific data submitted by the licensee regarding the FCS fuel oil storage tank design, surveillance data delineating a history of low water content in the storage tanks, the FCS diesel fuel oil testing program, and detailed procedures for sampling fuel oil and removing water from the fuel oil, the licensee proposed an interval for this surveillance of 92 days. Based on the staff review of plant specific information, the staff finds this change acceptable.
3.5 Proposed TS 5.22 Diesel Fuel Oil Testing Program The diesel fuel oil testing program is added as TS 5.22. The diesel fuel oil testing program includes purchasing, receipt testing of the new fuel, and periodic analysis of the stored fuel.
This program is aligned with NUREG-1432 with two exceptions that are discussed below.
The first exception of the FCS diesel fuel oil testing program to NUREG-1432 is the testing of new fuel. The STS call for a visual inspection of the new fuel oil. The proposed TS 5.22.a.3 adds an alternative method for testing the new fuel for contamination. The proposed change
will modify the method for testing new fuel oil by permitting the acceptability of the fuel oil to be determined based on its water and sediment content rather than by performing a visual inspection to confirm a "clear and bright" appearance as described in ASTM D-2276. Diesel fuel oil has a high sulfur content and is dyed in accordance with the Environmental Protection Agency mandated requirements. The presence of this dye does not permit use of the color scale in the "clear and bright" visual test. For this reason, an alternate method of testing for water and sediment, such as a centrifuge, is necessary. Because the proposed method of testing for water and sediment will yield more meaningful information regarding the fuel oil quality, the staff finds the change acceptable.
The second exception to NUREG-1432 that FCS proposes is the relocation of all references to specific ASTM standards from TS 5.22 to a licensee-controlled document. Changes to the licensee-controlled document are performed in accordance with the provisions of 10 CFR 50.59, "Changes, tests, and experiments." Relocation of the references to specific ASTM standards from the Administrative Controls Section of the TS to a licensee-controlled document provides flexibility to use the most up-to-date standards available without amending the TS in the future.
The staff finds the above changes to TS 5.22 acceptable. The addition of an alternate test method for new fuel (TS 5.22.a.3) will better ensure the quality of the fuel shipments at FCS.
The removal of specific ASTM references from the TS will reduce administrative burden, have no safety consequences, and will contribute to more efficient operation of the plant.
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 7526). 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 Contributors: J. Golla and M. Yoder Date: October 21, 2004