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Category:Letter type:LIC
MONTHYEARLIC-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) 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 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 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 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 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 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 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 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 LIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0004, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2022-02-17017 February 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-21-0008, Organizational and Management Change2021-10-28028 October 2021 Organizational and Management Change LIC-21-0007, ISFSI Only Emergency Plan Update2021-09-0808 September 2021 ISFSI Only Emergency Plan Update LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report2021-04-29029 April 2021 Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-21-0003, Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report2021-03-30030 March 2021 Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-21-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-22022 February 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0015, Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092)2020-07-29029 July 2020 Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092) LIC-20-0014, Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2020-07-15015 July 2020 Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-20-0012, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2020-05-18018 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool LIC-20-0011, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-05-0707 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2020-04-30030 April 2020 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-20-0008, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-04-13013 April 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0006, (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2020-03-26026 March 2020 (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-03-10010 March 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-02-27027 February 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0002, Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan2020-02-27027 February 2020 Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan LIC-20-0001, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-02-0606 February 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0025, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-12-19019 December 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0007, Post-Shutdown Decommissioning Activities Report2019-12-16016 December 2019 Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-19-0022, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-11-18018 November 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0018, Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2019-11-14014 November 2019 Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-19-0020, Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis2019-10-17017 October 2019 Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis LIC-19-0017, Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 20042019-08-0808 August 2019 Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 An LIC-19-0010, License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associa2019-05-20020 May 2019 License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated LIC-19-0008, Submittal of 2018 Annual Report2019-04-0404 April 2019 Submittal of 2018 Annual Report LIC-19-0004, Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP)2019-03-28028 March 2019 Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP) LIC-19-0005, 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report2019-03-28028 March 2019 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2019-02-28028 February 2019 License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme LIC-19-0003, Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation R2019-02-28028 February 2019 Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation Requ LIC-19-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-01-0303 January 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-18-0031, Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update2018-12-17017 December 2018 Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update LIC-18-0030, Request for Partial Site Release Phase 22018-11-12012 November 2018 Request for Partial Site Release Phase 2 LIC-18-0028, Letter of Intent to Submit Request for Additional Partial Site Release2018-10-18018 October 2018 Letter of Intent to Submit Request for Additional Partial Site Release 2024-06-18
[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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m -l Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 April 8, 2009 LIC-09-0028 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 (R.P. Clemens) to NRC (Document Control Desk), Annual Report for 2008 Loss of Coolant Accident (LOCA)/Emergency Core Cooling System (ECCS)
Models Pursuant to 10 CFR 50.46, dated April 3, 2009 (LIC-09-0026)
Subject:
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 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/error in the Small Break (SB) Loss-of-Coolant Accident (LOCA) and Large Break (LB)
LOCA ECCS models and evaluations. 10 CFR 50.46(a)(3)(i) states that 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 model, or is an accumulation of changes and errors such that the sum of the absolute magnitudes of the respective temperature changes is greater than 50°F.
The attached report identifies an error in the SB LOCA portion and an accumulation of errors in the LB LOCA portion associated with the quantification of PCT associated with various code errors identified in the AREVA (formerly Framatome ANP) model for Fort Calhoun Station (FCS), Unit No. 1. References 2 and 3, respectively, describe the SB and LB LOCA analysis methodology used by AREVA for the FCS Analysis of Record (AOR).
ACrn.
Employment with Equal Opportunity 4171
U.S. Nuclear Regulatory Commission LIC-09-0028 Page 2 If you should have any questions, please contact Mr. Bill R. Hansher at (402) 533-6894.
Sincerely/,/
P. Clemens Division Manager Nuclear Engineering Attachments:
- 1. 30-Day Report of Significant Change/Error in LOCA/ECCS Models
- 2. Fort Calhoun Station Small Break LOCA Margin Summary Sheet
- 3. Fort Calhoun Station Large Break LOCA Margin Summary Sheet
LIC-09-0028 Page 1 30-Day Report of Significant Change/Error in LOCA/ECCS Models An issue was discovered during the development of a new radiation heat transfer model (for Revision 2 of the Realistic Large Break LOCA (RLBLOCA) methodology). A significant discrepancy between the currently used model in S-RELAP5 for the RLBLOCA methodology and other published models was discovered. A well-known industry model was documented and installed into TRAC-B. Part of the documentation for that model is a figure that shows radiation heat transfer data versus the TRAC-B model and the Thomson model.
This figure has also been copied and published in other journals and documents.
The radiation to fluid heat transfer model currently employed in S-RELAP5 for LOCA analyses used the flawed figure as the data basis for determining coefficients for the correlation of emissivity of water vapor. The result is that the S-RELAP5 radiation to fluid correlation under predicts the radiative heat transfer.
This issue has been caused by flawed data used within the industrial community.
An evaluation has been performed to determine the impact on PCT. For the Fort Calhoun SB LOCA analysis, the PCT impact was estimated to be -64°F. For the Fort Calhoun LB LOCA analysis, the PCT impact was estimated to be -27 0 F.
This error includes a change of greater than 50°F in the SB LOCA PCT. The accumulation of the sum of the absolute magnitude of the previous year errors and this error for the LB LOCA PCT results in a change of greater than 50 0 F.
These changes for the SB and LB LOCA Analyses are subject to the 30-day reporting requirements of 10 CFR 50.46.
For previous years, the net change in the SB LOCA Analysis PCT 10 CFR 50.46 Model Assessment errors is -87F and the absolute change is +80 F (Reference 4).
For 2009, one error results in a net change in the SB LOCA PCT of -64°F. provides the SB LOCA Margin Summary Sheet for FCS. Because of the -72 0 F total errors, the SB LOCA PCT changed from the baseline value (reported in the FCS Updated Final Safety Analysis Report) of 1537°F to 1465 0 F.
The sum of the absolute values of the errors/changes in the SB LOCA analysis of record is +72°F.
For previous years, the net change in the LB LOCA Analysis PCT 10 CFR 50.46 Model Assessment errors is -13 0 F and the absolute change is +27°F (Reference 4). For 2009, one error results in a net change in the LB LOCA PCT of -27 F. provides the LB LOCA Margin Summary Sheet for FCS. Because of the -40°F total errors, the LB LOCA PCT changed from the baseline value (reported in the FCS Updated Final Safety Analysis Report) of 1636°F to 1596°F.
The sum of the absolute value of the errors/changes in the LB LOCA analysis of record is +54°F.
LIC-09-0028 Page 2 Since these results represent a quantification requiring no further analysis and FCS PCT values remain less that the 10 CFR 50.46(b)(1) acceptance criteria of 2200 0 F, no further analytical or operational mitigating strategies are required.
The Omaha Public Power District will be reanalyzing the SB LOCA and LB LOCA analyses for Extended Power Uprate (EPU), and the code changes will be incorporated. EPU is scheduled to be implemented beginning with Cycle 28 operations in the fall of 2012.
LIC-09-0028 Page 1 Small Break LOCA Margin Summary Sheet day Report Plant Name: Fort Calhoun Station Utility Name: Omaha Public Power District EvaluationModel: Small Break LOCA Net PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections- APCT = -8*F 8°F Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections- APCT = 0°F 0°F This year C. Current 10 CFR 50.46 Changes: - This Report
- 1. S-RELAP5 radiation to fluid correlation under APCT = -64°F 64*F predicts the radiative heat transfer Absolute Sum of 10 CFR 50.46 Changes APCT = 72°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 0 F.
LIC-09-0028 Page 1 Large Break LOCA Margin Summary Sheet - Annual Report Plant Name: Fort Calhoun Station Utility Name: Omaha Public Power District Evaluation Model: Large Break LOCA Net PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error, Corrections- APCT = -13'F 27F Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections- APCT = 0TF 0°F This year C. Current 10 CFR 50.46 Changes: - This Report
- 1. S-RELAP5 radiation to fluid correlation under APCT = -27F 27*F predicts the radiative heat transfer Absolute Sum of 10CFR 50.46 Changes APCT = 54TF 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 0 F.