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Category:Letter
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22159A2152022-06-28028 June 2022 Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report 2024-01-31
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARLIC-15-0059, Small Break Loss-of-Coolant Accident (SBLOCA) I Emergency Core Cooling System (ECCS) Evaluation Model Change/Error - 30-Day Report2015-04-24024 April 2015 Small Break Loss-of-Coolant Accident (SBLOCA) I Emergency Core Cooling System (ECCS) Evaluation Model Change/Error - 30-Day Report LIC-14-0115, Special Report on Inoperability of Containment Accident Radiation Monitor RM-091A/B for Post Accident Monitoring2014-09-25025 September 2014 Special Report on Inoperability of Containment Accident Radiation Monitor RM-091A/B for Post Accident Monitoring LIC-14-0105, Special Report on Inoperability of Containment Accident Radiation Monitor RM-091B for Post Accident Monitoring2014-08-20020 August 2014 Special Report on Inoperability of Containment Accident Radiation Monitor RM-091B for Post Accident Monitoring ML13266A1082013-09-20020 September 2013 30-Day Report of a Significant Change in the Loss-of-Coolant Accident(Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 LIC-09-0028, Omaha Public Power District - 30-Day Report of a Significant Change/Error in the Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.462009-04-0808 April 2009 Omaha Public Power District - 30-Day Report of a Significant Change/Error in the Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 LIC-07-0037, Fort Calhoun Station Unit 1, Special Report on the Containment Tendon Prestressing System, Free Water Found in Dome Tendons2007-05-25025 May 2007 Fort Calhoun Station Unit 1, Special Report on the Containment Tendon Prestressing System, Free Water Found in Dome Tendons ML0715100882007-05-25025 May 2007 Special Report on the Containment Tendon Prestressing System, Free Water Found in Dome Tendons 2015-04-24
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Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 May 25, 2007 LIC-07-0037 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
References:
- 1. Docket No. 50-285 2. NRC Regulatory Guide 1.35, "Inservice Inspection of Prestressed Concrete Containments," Revision 3 dated July 1990 3. American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section XI, Subsection IWL, 1992 Edition, 1992 Addenda
Subject:
Special Report on the Containment Tendon Prestressing System, Free Water found in Dome Tendons The Omaha Public Power District (OPPD) submits this special report pursuant to the requirements of Fort Calhoun Station, Unit No.1 (FCS) Technical Specification (TS) 5.9.3.b,"Special Reports." The FCS surveillance test acceptance criteria for the containment tendon prestressing system requires the absence of "free water" in the corrosion inhibiting grease. TS 5.19 requires an immediate investigation to determine the causes and extent of any non-conformance with the acceptance criteria and requires the results to be reported to the Commission within 90 days via a special report in accordance with TS 5.9.3.Precision Surveillance Corporation (PSC) completed the thirty-fifth year containment building prestressing system surveillance including the dome tendons on February 27, 2007 in accordance with References 2 and 3. Free water was found in one (1) dome tendon (D230P) randomly selected for testing. Inspections of the tendon anchor head and button heads found no corrosion.
One (1) of the ninety (90) effective wires was removed from tendon D230P and a small amount of corrosion was noted. The wire was sent to an offsite laboratory for additional inspection and testing. All conditions were satisfactory for tensioning tendon D230P and returning it to service.Grease caps on adjacent tendons were removed to inspect for free water and a small amount was found in tendon D23 IP, which did not warrant further testing.Temperatures were below freezing during the entire test period. When temperatures are not consistently above 60'F, removal, and replacement of corrosion inhibiting grease is not practical.
Employment with Equal Opportunity U.S. Nuclear Regulatory Commission LIC-07-0037 Page 2 Laboratory testing of the wire removed from tendon D230P was in accordance with Subsection IWL-2523 of the ASME Code and resulted in satisfactory values of yield strength, ultimate tensile strength, and elongation.
A pH of 8.6 was found in the water sample from tendon D230P.A pH value above 7.0 indicates the water is non-acidic and not conducive to aggressive corrosion.
Analyses conducted on corrosion medium samples showed acceptable reserve alkalinity, water content, and concentrations of water-soluble chlorides, nitrates, and sulfides.OPPD suspects that the free water entered tendons D230P and D231P through small cracks in the dome concrete.
However, the cracks are not accessible for visual inspection due to a concrete overlay on the dome perimeter, which allows a level work surface.OPPD will investigate the feasibility of using a crack sealant to block the suspected leak path.As a preventative measure, additional inspections are planned to check more tendons adjacent to tendon D230P for free water. The old grease will be replaced with new grease on any tendons found with free water inside. An additional wire will be removed from tendon D230P, and will be examined and tested in accordance with Subsection IWL-2523 of the ASME Code. These actions are considered regulatory commitments (AR 40538) and will be completed by July 31, 2008.Tests show that despite the presence of free water, corrosion has not degraded the strength of dome tendon D230P. Based on chemical analysis of the corrosion inhibiting grease, no significant corrosion of the tendon wire and anchorage components, and continued satisfactory tension measurements of the containment prestressing tendons, OPPD is confident in the ability of the containment structure to perform its safety related function.If you should have any questions or require additional information, please contact Mr. Thomas C. Matthews at (402) 533-6938.Sincerely, H. J. Faulhaber Division Manager Nuclear Engineering HJF/MLE/mle c: B. S. Mallett, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. D. Hanna, NRC Senior Resident Inspector