Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: LIC-13-0142, Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition, LIC-13-0158, Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition, LIC-13-0179, Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition, LIC-14-0004, Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition, ML11276A118, ML113260423, ML13256A110, ML14163A002, ML16103A348
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MONTHYEARML11276A1182011-09-28028 September 2011 Fort Calhoun Station - License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Other ML1132604232011-12-13013 December 2011 Online Reference Portal for National Fire Protection Association Standard (NFPA) 805 License Amendment Request Project stage: Other ML1135403342011-12-19019 December 2011 Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement LIC-11-0136, Clarification of Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2011 Edition)2011-12-22022 December 2011 Clarification of Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2011 Edition) Project stage: Supplement ML1136300832011-12-29029 December 2011 Acceptance Review Email, License Amendment Request to Adopt National Fire Protection Standard NFPA -805 Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generation Plants, Project stage: Acceptance Review LIC-12-0033, Submittal of Fire Dynamic Simulator (FDS) Input Files in Response to NRC NFPA 805 Transition License Amendment Request Audit Team Request at Fort Calhoun Station2012-03-20020 March 2012 Submittal of Fire Dynamic Simulator (FDS) Input Files in Response to NRC NFPA 805 Transition License Amendment Request Audit Team Request at Fort Calhoun Station Project stage: Request ML1210205742012-04-11011 April 2012 Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: Draft RAI ML1210205612012-04-11011 April 2012 Draft Request for Additional Information Email, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition). Project stage: Draft RAI ML1210400482012-04-26026 April 2012 Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: RAI LIC-12-0083, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition2012-07-24024 July 2012 Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition Project stage: Response to RAI LIC-12-0120, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station2012-08-24024 August 2012 Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station Project stage: Response to RAI LIC-12-0135, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station2012-09-27027 September 2012 Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station Project stage: Response to RAI ML13016A4322013-01-16016 January 2013 E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: RAI ML13053A2262013-02-22022 February 2013 Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. Project stage: Draft RAI LIC-13-0033, Omaha Public Power District'S, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station2013-04-23023 April 2013 Omaha Public Power District'S, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station Project stage: Request W3F1-2013-0022, Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 8052013-05-16016 May 2013 Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 Project stage: Request LIC-13-0060, Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station2013-05-21021 May 2013 Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station Project stage: Request ML13178A0352013-06-27027 June 2013 Email Request for Additional Information Round 3 (Afpb), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition). Project stage: RAI LIC-13-0096, Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 8052013-07-29029 July 2013 Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 Project stage: Request ML13226A1222013-08-14014 August 2013 Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: RAI ML13256A1102013-09-12012 September 2013 Safe Shutdown Analysis (SSA) RAI Response - NFPA-805 Transition (ME7244) Project stage: Other ML13270A2872013-09-27027 September 2013 Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: RAI LIC-13-0142, Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition2013-10-11011 October 2013 Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition Project stage: Other LIC-13-0158, Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition2013-11-0404 November 2013 Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition Project stage: Other LIC-13-0167, Safe Shutdown Analysis (SSA) RAI 17.02 Response - NFPA-805 Transition (ME7244)2013-11-11011 November 2013 Safe Shutdown Analysis (SSA) RAI 17.02 Response - NFPA-805 Transition (ME7244) Project stage: Request LIC-13-0179, Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition2013-12-18018 December 2013 Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition Project stage: Other LIC-14-0004, Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition2014-01-24024 January 2014 Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition Project stage: Other ML14036A0682014-02-18018 February 2014 Request for Withholding Information from Public Disclosure, 12/9/11 Affidavit Executed by C. M. Molnar, Westinghouse, LTR-RAM-II-10-046, Revision 1, Dated 4/22/2011 Project stage: Withholding Request Acceptance ML14036A0832014-02-18018 February 2014 Request for Withholding Information from Public Disclosure, 3/14/12 Affidavit Executed by J. A. Gresham, Westinghouse, Re.: Compact Containing Fire Dynamic Simulator Input Project stage: Withholding Request Acceptance ML14051A3972014-02-20020 February 2014 NFPA 805 IE PRA F&O Tables Project stage: Request ML14051A3882014-02-20020 February 2014 NFPA 805 Fpra F&O Tables Project stage: Request ML14070A5912014-02-28028 February 2014 Supplemental Response to Safe Shutdown Analyses (SSA) Request for Additional Information (RAI) 06 - NFPA-805 Transition Project stage: Supplement ML14115A2972014-04-10010 April 2014 Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Supplement ML14115A2982014-04-10010 April 2014 Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance -Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Supplement LIC-14-0042, Enclosure 2: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants2014-04-10010 April 2014 Enclosure 2: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Supplement ML14122A2452014-05-22022 May 2014 Request for Withholding Information from Public Disclosure, 3/26/13 Affidavit Executed by C. M. Molnar, Westinghouse, Re.: LTR-RAM-II-10-046, Rev. 3 Project stage: Withholding Request Acceptance LIC-14-0075, Request Clarifications to Draft National Fire Protection Association (NFPA) 805 Safety Evaluation Report2014-06-11011 June 2014 Request Clarifications to Draft National Fire Protection Association (NFPA) 805 Safety Evaluation Report Project stage: Request 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) Project stage: Approval ML14163A0022014-06-16016 June 2014 Summary of Audit Conducted March 5-9, 2012, Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants Project stage: Other ML16103A3482016-04-0404 April 2016 Ft. Calhoun, Unit 1 - License Amendment Request (LAR) 16-01; Revised Commitment to Modify FCS Plant Systems as Part of the Implementation of NFPA 805 Project stage: Other LIC-16-0099, License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program2016-11-18018 November 2016 License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program Project stage: Request 2013-04-23
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Category:Drawing
MONTHYEARML22081A0422022-03-10010 March 2022 Independent Spent Fuel Storage Installation, DSAR Figures Section-01 - Part 2 of 4 ML22081A0432022-03-10010 March 2022 Independent Spent Fuel Storage Installation, DSAR Figures Section-02 - Part 3 of 4 LIC-22-0002, Independent Spent Fuel Storage Installation, DSAR Figures Section-12 - Part 4 of 42022-03-10010 March 2022 Independent Spent Fuel Storage Installation, DSAR Figures Section-12 - Part 4 of 4 ML20170A4522020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Appendix-F ML20170A4532020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 01 ML20170A4542020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 02 ML20170A4562020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 03 ML20170A4572020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section-07 ML20170A4582020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 08 ML20170A4592020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 09 ML20170A4602020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 11 ML20170A4612020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 12 ML20170A4622020-04-30030 April 2020 Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Figures, Section 14 LIC-18-0023, Partial Site Release Survey - Background Sample Locations, Rev. 12018-06-26026 June 2018 Partial Site Release Survey - Background Sample Locations, Rev. 1 ML13256A1102013-09-12012 September 2013 Safe Shutdown Analysis (SSA) RAI Response - NFPA-805 Transition (ME7244) LIC-03-0069, Transmittal of Boundary Drawings Associated with Fort Calhoun Station Unit 1 Annual Update to Application for Renewed Operating License2003-05-16016 May 2003 Transmittal of Boundary Drawings Associated with Fort Calhoun Station Unit 1 Annual Update to Application for Renewed Operating License LIC-03-0046, Drawing, Detailed Map of Area Around Fort Calhoun Station.2003-04-25025 April 2003 Drawing, Detailed Map of Area Around Fort Calhoun Station. ML0307706812003-02-18018 February 2003 Drawing 11405-M-1, Rev 27, Containment Heating Cooling & Ventilating Flow Diagram P & Id. Sheet 2 ML0236002462002-12-19019 December 2002 Drawing SBO Figure 8 1-1, Simplified One Line Diagram of Substation/Sbo. ML0236002402002-12-19019 December 2002 Drawing CND-E-2935, Rev. 7, Seal Housing Assy. Details. ML0236002262002-12-19019 December 2002 Drawing 11405-M-259, Rev. 107, Flow Diagram Portable & Service Water System P & Id. Sheet 1 LIC-02-0136, Drawing - 11405-M-42, Rev.85, Nitrogen, Hydrogen, Methane, Propane & Oxygen Gas Flow Diagram P & Id. Sheet 12002-11-22022 November 2002 Drawing - 11405-M-42, Rev.85, Nitrogen, Hydrogen, Methane, Propane & Oxygen Gas Flow Diagram P & Id. Sheet 1 ML0236001982002-10-27027 October 2002 Drawing 11405-A-259, Rev. 34, Turbine & Office Building Plan at Elevation 1011' - 0 & 1019' - 6 P&Id. ML0307706982002-08-12012 August 2002 Drawing 11405-M-257, Rev 23, Flow Diagram Circulating Water P & Id. Sheet 2 ML0307706832002-08-12012 August 2002 Drawing 11405-M-257, Rev 23, Flow Diagram Circulating Water P & Id. Sheet 2 ML0206002212002-02-28028 February 2002 Use of Blair High School Auditorium for Public Meeting - Diagram Showing the Proposed Locations of Tables, Microphones, Etc ML0208002952002-02-27027 February 2002 Drawing RM19-1, Fort Calhoun Station, Fire Area 32, Appendix R Cable Locations LIC-02-0007, Correction to Fort Calhoun Station'S (FCS) Discussion of Control Element Drive Mechanism (CEDM) Housing Reliability Figure 42002-02-0707 February 2002 Correction to Fort Calhoun Station'S (FCS) Discussion of Control Element Drive Mechanism (CEDM) Housing Reliability Figure 4 ML0202905322002-01-0909 January 2002 Drawing 11405-M-259, Rev 107, Flow Diagram Potable & Service Water System P & Id. Sheet 1 ML0202905412002-01-0909 January 2002 Drawing 11405-M-266, Rev 24, Fire Protection Flow Diagram P & Id. Sheet 1B ML0203105342002-01-0909 January 2002 Drawing E-23866-163-007, Rev 09, C.E.D.M. Installation Dwg. ML0203105352002-01-0909 January 2002 Drawing E-23866-165-026, Rev 2, In-Core Instrument Flanges Interface. ML0203105362002-01-0909 January 2002 Drawing E-232-408-5, General Arrangement Elevation for Omaha Power 140 I.D. Pwr. ML0203105412002-01-0909 January 2002 Drawing J-23866-164-033, Rev 06, Fuel Alignment Plate. ML0203105552002-01-0909 January 2002 Drawing J-23866-164-011, Rev 11, Core Support Assy. ML0203105562002-01-0909 January 2002 Drawing J-23866-164-013, Rev 05, Core Support Barrel. ML0203105582002-01-0909 January 2002 Drawing J-23866-164-031, Rev 10 ML0203105572002-01-0909 January 2002 Drawing J-23866-164-018, Rev 02, Core Support Plate Assy. ML0203706122002-01-0909 January 2002 Drawing J-23866-164-012, Rev 04, Core Support Barrel Lower Section Assy. ML0203706142002-01-0909 January 2002 Drawing J-23866-164-016 2022-03-10
[Table view] Category:Letter
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22159A2152022-06-28028 June 2022 Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report 2024-01-31
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jjjjjjjj 0maIIa PuIJ/Jt; Power IJIs:IIict 444 South 1~ Street Mall Omaha, NE 68102-2247 LlC-13-0129 September 12, 2013 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No.1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
References:
See Reference List on Page 3
SUBJECT:
Safe Shutdown Analysis (SSA) RAI Response - NFPA-805 Transition (ME7244)
The Omaha Public Power District's (OPPD's) response to the Nuclear Regulatory Commission's (NRC's) request for additional information (RAI) regarding the safe shutdown analysis (SSA) is provided in the attachments to this letter. As noted in the Reference 11 email.this RAI is from the second set of the third round of RAls regarding the license amendment request (LAR) to adopt National Fire Protection Association (NFPA) 805 at the Fort Calhoun Station (FCS). OPPD agreed to provide a response to this RAI by September 13, 2013.
In the Reference 1 LAR, OPPD requested an amendment to Renewed Facility Operating License No. DPR-40 for FCS, Unit No.1, to adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition). The NRC staff reviewed OPPD's application and determined that additional information was required in order to complete their review and subsequently transmitted RAls via References 2, 6 and 9. OPPD provided responses to these RAls in References 3, 4, 5, 7, 8, and 10. The NRC indicated that the staff had reviewed the information provided by the licensee [in References 3, 4, 5, 7, 8, and 10] and determined that additional information specified in the Reference 11 email is needed for the staff to complete its review.
In Reference 11, the NRC notified OPPD that additional information is required in order to complete its review. Attachments 1 and 2 of this submittal contain the response to the Safe Shutdown Analysis (SSA) RAI 17.01, which OPPD agreed to provide by September 13, 2013. As noted in Reference 11, a response to the RAls listed below will be provided in accordance with the following schedule:
- PRA RAls 01.i.02, 01.j.02, 01.j.03, 23.01, and 27 responses to be provided by October 7, 2013.
- PRA RAls 07.02, 19.01, 24, 25, and 26 responses to be provided by November 6, 2013.
Employment wfth EqualOpportunio/
U. S. Nuclear Regulatory Commission LlC-13-0129 Page 2 There are no new regulatory commitments being made in this letter as a result of the enclosed NFPA 805 RAI responses. Please note, as indicated in References 3, 4, 7, 8, and 10, OPPD plans to supplement the NFPA 805 transition LAR, which will reflect the applicable information delineated in the enclosed RAI responses. The LAR supplement is being tracked by AR 48249.
In accordance with 10 CFR 50.91, a copy of this letter, without the attachments, is being provided to the designated State of Nebraska official.
If you should have any questions regarding this submittal or require additional information, please contact Mr. Bill R. Hansher, Supervisor-Nuclear Licensing, at 402-533-6894.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September 12, 2013.
ouis P. Cortopassi Site Vice President and CNO LPC/BJVImle Attachments: 1. Response to SSA RA117.01
- 2. Circuit Design Sketch and Description of Design Option 1 c: S. A. Reynolds, Acting NRC Regional Administrator, Region IV J. W. Sebrosky, NRC Senior Project Manager L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector Manager Radiation Control Program, Nebraska Health & Human Services, R & L Public Health Assurance, State of Nebraska (w/out attachments)
U. S. Nuclear Regulatory Commission UC-13-0129 Page 3 Reference List
- 1. Letter from OPPD (J. A. Reinhart) to NRC (Document Control Desk), License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) at Fort Calhoun Station, dated September 28, 2011 (UC-11-0099) (ML112760660)
- 2. Letter from the NRC (L. E. Wilkins) to OPPD (David J. Bannister), Fort Calhoun Station, Unit No.1 - Request for Additional Information Re: License Amendment Request to Adopt National Fire Protection Agency Standard NFPA 805 (TAC No. ME7244), dated April 26, 2012 (NRC-12-0041) (ML121040048)
- 3. Letter from OPPD (D. J. Bannister) to NRC (Document Control Desk), Responses to Requests for Additional Information Re: License Amendment Request 10-07 to Adopt NFPA 805, *Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants," 2001 Edition, at Fort Calhoun Station, dated July 24, 2012 (UC-12-0083)
(ML12208A131 )
- 4. Letter from OPPD (D. J. Bannister) to NRC (Document Control Desk), Responses to Requests for Additional Information Re: License Amendment Request 10-07 to Adopt NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants," 2001 Edition, at Fort Calhoun Station, dated August 24, 2012 (UC-12-0120)
(ML12240A151)
- 5. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), Responses to Requests for Additional Information Re: License Amendment Request 10-07 to Adopt NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants," 2001 Edition, at Fort Calhoun Station, September 27, 2012 (UC-12-0135)
(ML12276A046)
- 6. Email from NRC (L. E. Wilkins) to OPPD (D. L. Lippy), DRAFT: Fort Calhoun NFPA 805, Second Round (ME7244), dated February 22,2013 (NRC-13-0014)
- 7. Letter from OPPD (M. J. Prospero) to NRC (Document Control Desk), Responses to Second Request for Additional Information Re: License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station (TAC No. ME7244), dated April 23, 2013 (UC-13-0033)
- 8. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), Remaining Responses to Second Request for Additional Information Re: License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station (TAC No. ME7244), dated May 21, 2013 (UC 0060)
- 9. Email fromNRC(J.M.Sebrosky)toOPPD(D.L.Lippy).FortCalhounNFPA805.Third Round of RAls (ME7244), dated June 27,2013 (NRC-13-0081)
- 10. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station (TAC No. ME7244), dated July 29,2013 (UC-13-0096)
- 11. Email fromNRC(L.E.Wilkins)toOPPD(D.L.Lippy).FortCalhounNFPA805.Third Round, Second Part, of RAls (ME7244), dated August 14, 2013 (NRC-13-0102)
LlC-13-0129 Page 1 Omaha Public Power District (OPPD)
Response to Safe Shutdown Analysis (SSA) RAI17 .01 License Amendment Request to Adopt National Fire Protection Association Standard 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants at Fort Calhoun Station, Unit 1 (TAC No. ME7244)
By letter dated September 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112760660), as supplemented by letters dated December 19 and 22, 2011, and March 20, 2012 (ADAMS Accession Nos. ML113540334, ML11363AOn, and ML12083A147, respectively), Omaha Public Power District, (the Licensee), submitted a license amendment request (LAR) to transition their fire protection licensing basis at the Fort Calhoun Station, Unit 1, from Title 10 of the Code of Federal Regulations (CFR), Section 50.48(b), to 10CFR50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805). A review team, consisting of U.S. Nuclear Regulatory Commission (NRC) staff and contractors from Pacific Northwest National Laboratory (PNNL) and the Center for Nuclear Waste Regulatory Analyses (CNWRA) participated in a regulatory audit of Fort Calhoun in Blair, NE from March 5
-9,2012. By letter dated April 26, 2012, (ADAMS Accession No. ML12198A406) the NRC issued requests for additional information (RAls). By letters dated July 24,2012 (ADAMS Accession No. ML12208A131), August 24,2012 (ADAMS Accession No. ML12240A151), and September 27,2012 (ADAMS Accession No. ML12276A046) the licensee provided responses to the RAls.
The NRC staff reviewed the information provided by the licensee in response to the first set of RAls and determined that additional information was needed for the staff to complete its evaluation. Consequently, the staff issued a second round of RAis on February 22, 2013, (ADAMS Accession No. ML13053A226) and a third round of RAls on June 27, 2013 (ADAMS Accession No. ML13178A035). The licensee responded to these RAis in letters dated April 23, 2013 (ADAMS Accession No. ML13116A015), May 21, 2013 (ADAMS Accession No. ML13144A814), and July 29,2013 (ADAMS Accession No. ML13211A055).
The U.S. NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. These RAls can be found below. The NRC considers these RAls to be the second set of the third round of RAls. Based on discussions with you on August 13, 2013, it was agreed that a response to the RAls found below will be provided in accordance with the following schedule:
- PRA RAls 01.i.02, 01.j.02, 01.j.03, 23.01, and 27 responses to be provided by October 7, 2013
- PRA RAls 07.02, 19.01, 24, 25, and 26 responses to be provided by November 6, 2013.
In addition, as discussed with you during the August 13, 2013, phone call the staff has determined that you no longer need to provide a response to SSA RAI 07.01 that was issued to you on June 27, 2013 (ADAMS Accession No. ML13178A035). The staff determined that SSA RA107.01 response is not needed in order for the staff to complete its safety evaluation. The staff also discussed with you during the August 13, 2013, phone call that the response to PRA RAI 24 should include two additional sensitivity studies as a result of issues that were raised during a July 22 through July 24, inspection at your site.
LlC-13-0129 Page 2 Should the NRC determine that the RAls found below are no longer necessary prior to the dates found above, the request will be withdrawn. H circumstances result in the need to revise the requested response date, please contact me or Joe Sebrosky.
SSA RAI 17.01 License Amendment Request, Attachment S, Table S-2, "Plant Modifications Committed," Item REC-117, states:
"Modification to change the normal operating alignment for 480 V load center tie breakers BT-1B4A, BT-1B3B, and BT-1B4C from normally open and racked-in, to normally racked-out (or otherwise disabled from spuriously closing due to fire damage to DC breaker control circuits in the opposite Train 4kV switchgear room, main control room, or cable spreading room). This modification addresses the issue associated with electrical failure resulting from spurious connection of out-of-synch power sources (offsite power to diesel generator, diesel generator to diesel generator)."
It is further stated that: "The proposed modification will maintain breaker manual trip capability from main control room, protective trip, automatic load shed trip and accident signal trip for fire areas 36A, 36B, 41 and 42."
According to NRC Special Inspection Report dated March 12, 2012 (ADAMS Accession No. ML12072A128), there are interconnecting control wires (operated at 125 V DC) between 480V tie breakers in Electrical Switchgear Fire Areas 36A (East Switchgear) and 36B (West Switchgear) (typical - between breakers BT-1B3A and BT-1B4A). These wires are used in the control circuitry of the breakers. A fire in these breakers in either Switchgear Fire Area 36A or 36B can cause damage to the control wires (such as shorts to ground) in the opposite area breakers.
During a recent inspection conducted from July 22, 2013 to July 24, 2013, Office of Nuclear Reactor Regulation (NRR) reviewers questioned the plant technical staff about the potential negative impact of performing the design change (modification) to rack out the normally open cross-tie breakers on the 480V AC switchgear. Discussions with plant staff indicate that a contingency plan exists to modify the control circuit to preclude spurious closure should the modification to rack out the breaker be deemed impractical.
By letter dated September 18, 2011, the licensee stated, " *.*(or otherwise disabled from spuriously closing due to fire damage to the DC breaker control circuits in the opposite train 4kV switchgear room ... )." The committed modification is not specified in sufficient detail for the NRC staff to determine its acceptability due to the open-ended parenthetical. Please provide a written description of the specific modification that will be implemented as part of the NFPA 805 transition as well as conceptual circuit design sketches indicating the existing portions of the circuit as well as those parts being added/modified.
OPPD Response to SSA RAI 17.01 A circuit design sketch and written description of the modification that will be implemented as part of the NFPA 805 transition is attached.
LlC-13-0 129 Page 1 CABlE A
.~
Cables A & B added to circuit.
IB~
rC~A sw MCB
~B TO AN1'J.PIJMP RELAY TOCLOSECOL--_ _
CABlEB
¥-
MCB SW MCB
~A BUS REC-117 - Proposed Design Option Circuit modification to prevent spurious closure of normally open bus tie breaker resulting from hot shorts.
The above figure shows the proposed circuit modification to prevent spurious closure of the normally open bus tie breakers BT-1B4A, BT-1B3B, and BT-1B4C. Contacts from the existing breaker control switch (SW) will be added to the breaker close circuit to provide isolation to the close coil thereby preventing spurious breaker closure from a fire induced hot short.
This modification will allow the Main Control Room operator to electrically open or trip the associated breaker from the Main Control Room when the associated breaker control switch is taken out of the "pull-ta-Iock" position.
Notes:
=
BUS termination at 480V Island Bus
=
MCB termination at Main Control Board in Main Control Room SW = new breaker control switch in MCB which incorporates a "pull to lock" position (contacts are break before make).
Same switch taken to close will close tie breaker (close contacts not shown). Same switch taken to trip position will trip tie breaker (trip contacts not shown).
Cable B is required to be thermoset, with no other conductors utilized other than the two conductors identified above.
Reference:
11405-E-18 Sheet 3 - breaker BT-1 84A control schematic 11405-E-18 Sheet 5 - breaker BT-1 B3B control schematic 11405-E-19 Sheet 1 - breaker BT-1 B4C control schematic 012484392 Sheet 1 - G.E. schematic for breaker close circuit internal wiring