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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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DjjjjD Omaha Pub/it: Power DIstrict 444 South 1(11' Street Mall Omaha, NE 68102-2247 September 20,2013 LlC-13-0133 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
References:
- 1. Docket 50-285
- 2. EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," Framatome ANP, INC., March 2001
- 3. EMF-2103(P)(A), Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Framatome ANP, Inc., April 2003.
- 4. Letter from OPPD (J. B. Herman) to NRC (Document Control Desk), Annual Report for 2011 Loss-of-Coolant Accident/Emergency Core Cooling System (ECCS) Models pursuant to 10 CFR 50.46, dated April 27, 2012 (LlC-12-0053)
- 5. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), Annual Report for 2012 Loss-of-Coolant Accident/Emergency Core Cooling System (ECCS) Models pursuant to 10 CFR 50.46, dated April 30, 2013 (LlC-13-0056)
Subject:
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 In accordance with 10 CFR 50.46(a)(3)(ii), the Omaha Public Power District (OPPD) is submitting a 30-day 10 CFR 50.46 report of a significant change in the Small Break Loss-of-Coolant Accident (SBLOCA) ECCS model and evaluation. 10 CFR 50.46(a)(3)(i) states: for this purpose: a significant change or error is one that results in a calculated peak fuel cladding temperature [PCT] different by more than 50°F from the temperature calculated for the limiting transient using the last acceptable modeJ, or is a cumulation of changes and errors such that the sum of the absolute magnitudes of the respective temperature changes is greater than 50°F.
Omaha Public Power District communicated to AREVA the need to evaluate a High Pressure Safety Injection (HPSI) flow reduction for the SBLOCA and Realistic Large Break (RLB) LOCA analyses as the result of a modification needed to prevent HPSI pump runout. This modification is currently undergoing system acceptance review by plant personnel.
The attached report identifies a change in the SBLOCA analysis in which a reduction in the credited HPSI flow rate has increased the expected PCT from the event. The RLBLOCA has not been adversely affected but is also reported for completeness.
There are no regulatory commitments contained in this submittal.
Employment with Equal Opportunity
U. S. Nuclear Regulatory Commission LlC-13-0133 Page 2 If you should have any questions, please contact Mr. Bill Hansher at (402) 533-6894.
ouis P. Cortopassi Site Vice President and CNO LPC/TAH/brh Attachment c: S. A. Reynolds, Acting NRC Regional Administrator, Region IV J. M. Sebrosky, NRC Senior Project Manager L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector
L1C-13-0133 Attachment Page 1 Evaluation of the Reduction of HPSI Delivery Flow for RLBLOCA Analysis For the RLBLOCA analysis, the timing of the event, the overall contribution of HPSI flow compared to total ECCS flow, and the reactor vessel downcomer inventory have been evaluated to assess the impact of the HPSI flow reduction. As a result of the evaluation, the HPSI flow reduction has been determined to have no impact on the Analysis of Record (AOR) limiting PCT. The PCT for RLBLOCA is 1581°F.
For the purpose of 10 CFR 50.46, no change occurred in the RLBLOCA, but the current RLBLOCA AOR estimated changes are greater than 50°F. OPPD plans to submit a new RLBLOCA analysis using Revision 3 of Reference 3 within one year of its approval by the NRC. (AR 60118)
Evaluation of the Reduction of HPSI Delivery Flow for SBLOCA Analysis The SBLOCA analysis has been re-evaluated to quantify the impact of the HPSI flow reduction.
In the AOR, the limiting break size reported corresponds to a 3.5 inch diameter break. With the HPSI flow reduction, the new limiting break size was identified as a 3.0 inch diameter break. The smaller break deploys the safety injection tanks later, due to the slower primary system depressurization. This effect, combined with the reduction in HPSI flow, contributes to the rise in the limiting PCT.
The PCT impact of the HPSI flow reduction for the Fort Calhoun SBLOCA AOR is +309°F. In combination with changes/errors from previous years, this +309°F changes the SBLOCA from the baseline value (153rF) reported in the FCS USAR to 1746°F.
Evaluation of the Reduction of HPSI Delivery Flow with Methodology Changes for SBLOCA Analysis In light of the recent NRC request for the Millstone Nuclear Power Plant (ML13074A795 and ML13192A102), AREVA re-analyzed the SBLOCA event with the HPSI flow reduction while incorporating the items introduced in Supplement 1 of Reference 2 which have the largest impact on the transient. Specifically, the following items were incorporated:
- Spectrum of break sizes analyzed according to the Supplement 1 of Reference 2.
- Loop seal clearing according to Supplement 1 of Reference 2.
- Core bypass model: the gaps identified in Supplement 1 of Reference 2 are assumed closed for the entire simulation.
The evaluation includes the methodology changes and the HPSI flow reduction. The SBLOCA analysis utilizing the changes above from Supplement 1 of Reference 2 resulted in a new limiting PCT of 1513°F (a decrease of 233°F) for a 3.4 inch break. This PCT addresses all the items in the rack-ups reported since 2006.
L1C-13-0133 Attachment Page 2 Large Break LOCA Margin Summary Sheet Plant Name: Fort Calhoun Station, Unit No.1 Utility Name: Omaha Public Power District Evaluation Model: Large Break LOCA Net PCT Effect Absolute
(~PCT) PCT Effect Prior 10 CFR S0.46 Changes or Error Corrections -SsoF 8soF A.
- Previous Years 10 CFR S0.46 Changes or Error Corrections - OaF B. +O°F HPSI Pump Runout Prevention Modification C. Absolute Sum of 10 CFR S0.46 Changes 8soF The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of the PCT impact for changes and errors identified since this analysis is less than 2200°F. The Net PCT Effect was reported incorrectly in the 2012 report as -62°F (Reference S).
The Net PCT reported in the 2011 report (Reference 4) was -62°F for previous years, +8°F for the current year, which results in a -S4°F for net effects. An additional Net PCT Effect of -1°F change resulting from a SO.S9 activity (Cycle 2S core bypass change) implemented in 2008 resulting in the Net PCT Effect of -SsoF. This also results in an Absolute PCT Effect of 8soF versus 84°F reported in Reference S. This reporting error has been entered into the FCS corrective action program.
Small Break LOCA Margin Summary Sheet Plant Name: Fort Calhoun Station, Unit No.1 Utility Name: Omaha Public Power District Evaluation Model: Small Break LOCA Net PCT Effect Absolute
(~PCT) PCT Effect Prior 10 CFR S0.46 Changes or Error Corrections A. -100°F 108°F
- Previous Years 10 CFR S0.46 Changes or Error Corrections -
B. +309°F 309°F HPSI Pump Runout Prevention Modification C. Absolute Sum of 10 CFR S0.46 Changes 417°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of the PCT impact for changes and errors identified since this analysis is less than 2200°F