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Category:Letter type:LIC
MONTHYEARLIC-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 LIC-18-0027, Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2018-10-0303 October 2018 Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update LIC-18-0003, License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool2018-09-28028 September 2018 License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool LIC-18-0025, Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 20192018-07-19019 July 2018 Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 2019 LIC-18-0023, Fort Calhoun Station, Unit 1 Request for Partial Site Release2018-06-29029 June 2018 Fort Calhoun Station, Unit 1 Request for Partial Site Release LIC-18-0021, Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan)2018-06-0606 June 2018 Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan) LIC-18-0017, Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy2018-04-26026 April 2018 Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy 2023-08-24
[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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~~9 UiiiiU Omaha Pub/I& Pawer Dlslrlt:I 444 South 1ff' Street Mall Omaha, NE 68102-2247 LIC-15-0059 10 CFR 50.46 April 24, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Fort Calhoun Station (FCS), Unit 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
Subject:
Small Break Loss-of-Coolant Accident (SBLOCA) I Emergency Core Cooling System (ECCS) Evaluation Model Change/Error Day Report
References:
- 1. Letter from OPPD (M. J. Prospero) to NRC (Document Control Desk),
"Annual Report for 2013 Loss-of-Coolant Accident (LOCA)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46," dated April 25, 2014 (ML14118A208) (LIC-14-0062)
- 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.
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), the Omaha Public Power District (OPPD) is submitting the attached information to fulfill the 30-day reporting requirement for Fort Calhoun Station (FCS), Unit No. 1.
FCS is currently in Refueling Outage 27, which began on April 11, 2015. Per the current schedule, FCS will re-load the core in early May 2015 for Operating Cycle 28 and at that time, will implement a design change for the initial fill gas pressurization of new fuel rods. This change is intended to provide more margin in the reload analysis for internal rod pressure. This design change decreases the initial fill gas pressure of the new U02 fuel rods from 390 psia to 330 psia, which is estimated to increase the peak clad temperature (PCT) for the small break loss-of-coolant accident (SBLOCA) analysis by +31°F. The cumulative effect of the design change and a prior +23°F error found to impact the 2014 annual 10 CFR 50.46 report necessitates the submittal of this report. For the SBLOCA AOR, this results in a total PCT of 1800°F.
The attached report describes the impact of the design change and the error on the SBLOCA analysis of record (AOR), which uses the Reference 2 methodology. These issues had no material impact on the realistic large break loss-of-coolant accident (RLBLOCA) AOR, which uses the Reference 3 methodology. For the RLBLOCA AOR, the estimated impact of the Cycle 28 U02 initial fuel fill gas pressurization design change on calculated PCT is 0°F resulting in a Employment with Equal Opportunity
U. S. Nuclear Regulatory Commission LIC-15-0059 Page2 total PCT of 1587°F. Additional discussion regarding the impact on the RLBLOCA AOR will be provided in the annual 10 CFR 50.46 report.
There are no regulatory commitments contained in this submittal.
If you should have any questions, please contact Mr. Bill Hansher at (402) 533-6894.
LPC/SEC/mle Attachments: 1. 30-Day Report of Significant Change in LOCNECCS Models
- 2. Fort Calhoun Station Small Break LOCA Margin Summary Sheet c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Project Manager S. M. Schneider, NRC Senior Resident Inspector
LIC-15-0059 Page 1 30-Day Report for Significant Change in LOCA/ECCS Models Evaluation of Design Change to Initial Fuel Rod Pressurization for Cycle 28 For Operating Cycle 28, Fort Calhoun Station (FCS), Unit No. 1 is implementing a change in fuel rod fill gas initial pressurization. The initial fill gas pressure of the U02 fuel rods has been reduced from 390 psia to 330 psia in order to optimize rod internal pressure margin by up to 170 psia while maintaining up to 0.750 mils of margin on creep collapse. The U02 fuel rods with M5 cladding being provided to FCS at an initial fill gas pressure of 330 psia continue to have sufficient design margin.
AREVA (formerly Framatome ANP) performed an operability assessment on the impact of thermal conductivity degradation (TCD) on fuel temperatures and hot free volumes in the RODEX2 fuel performance code used for small break loss-of-coolant accident (SBLOCA) analysis. The current Operating Cycle (27) was assessed and it was concluded that all fuel rods met the criteria for rod internal pressure and fuel-clad liftoff (approximately 2835 psia versus a criterion of 2900 psia). The assessment also noted a reduction of margin on end-of-cycle (EOC) rod internal pressure.
For the SBLOCA analysis, the reduction in fuel rod fill gas internal pressure affects the swell and rupture model. The SBLOCA transient is a slow progressing transient with peak clad temperature (PCT) occurring later in the event as compared to the realistic large break loss-of-coolant accident (RLBLOCA) transient. A change in fuel rod internal pressure affects the timing of cladding rupture, which could result in a change to PCT time leading to a change in the PCT calculated oxidation. Therefore, AREVA performed a sensitivity study to evaluate the impact on the SBLOCA analysis-of-record (AOR) PCT. The limiting case and multiple break sizes around the limiting case were rerun with the reduced fuel rod internal pressure.
For the RLBLOCA analysis, the swell and rupture model is not incorporated on plant specific applications as it is considered a benefit in the PCT calculation. The relocation phenomenon is not evaluated for FCS as the AOR PCT results are below 1850°F and the phenomenon is not significant below this threshold. In the AOR, the PCT is not driven by the rupture node or rupture time and changes in the initial rod pressure do not have an effect on the estimation of PCT.
For the FCS SBLOCA analysis, the calculated PCT impact was estimated to be +31°F with a PCT of 1800°F. For the FCS RLBLOCA analysis, the calculated PCT impact was estimated to be +0°F with a PCT of 1587°F.
AREVA Condition Report (CR) 2012-8371 In addition to the +31°F impact on PCT resulting from reduced U02 fuel rod initial fill gas pressure, a non-conservatism in AREVA's correlation for vapor absorptivity used in S-RELAP5 was discovered. In AREVA CR 2012-8371, it was determined that the correlation for vapor absorptivity used in S-RELAP5 was being applied outside of its intended range of applicability.
The PCT impact of the error on the FCS SBLOCA AOR is +23°F, which raises the evaluated PCT during a limiting SBLOCA to 1769°F compared to the limit allowed in 10 CFR 50.46 of 2200°F. There was no impact to PCT for the RLBLOCA transient. The cumulative effect of the design change discussed above and this error applicable to the Cycle 28 core is +54°F.
LIC-1 S-OOS9 Page 1 Small Break LOCA Margin Summary Sheet day Report Plant Name: Fort Calhoun Station, Unit No. 1 - Cycle 28 Utility Name: Omaha Public Power District ECCS Evaluation Model: EMF-2482P Report Revision Date: April 24, 2015 Current Cycle: 27 ANALYSIS OF RECORD Evaluation Method: EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAPS Based,"
Framatome ANP, Inc., March 2001.
Calculations: AREVA Calculation 32-9016476-000, Revision 0, "Fort Calhoun Cycle 24 SBLOCA Analysis."
AREVA Calculation 32-9130020-001, Revision 1, "Fort Calhoun SBLOCA Analysis with Reduced HPSI Flow."
Fuel Type: AREVA HTP 14x14 MS Limiting Fuel Type: AREVA HTP 14x14 MS Limiting Single Failure: Loss of one ECCS pumped injection train Limiting Break Size/Location: 3.S inch break size Reference PCT: 1S37°F LIC-15-0059 Page2 MARGIN ALLOCATION Evaluation Model: Small Break LOCA Net PCT Absolute Total PCT Effect (~PCT) PCT Effect Prior 10 CFR 50.46 Changes or Error A Corrections - 2013, HPSI Pump Runout +309°F 417°F 1746°F Prevention Modification (FAB 13-00350) 10 CFR 50.46 Changes or Error B. Corrections - 2014, S-RELAP5 Vapor +23°F 23°F 1769°F Absorptivity Correlation (FAB14-00196) 10 CFR 50.46 Changes or Error Corrections - 2014, Change to Initial C. +31°F 31°F 1800°F Fuel Rod Pressurization (FAB-14-00609-001)
Absolute Sum of 10 CFR 50.46 Changes 471°F The absolute sum of the PCT from the most recent 10 CFR 50.46 report using an acceptable evaluation model and the estimates of the PCT impact for changes and errors identified since that report is +54°F. The sum of the PCT from the SBLOCA AOR and these errors is 1800°F, which is still within the 2200°F criterion described in 10 CFR 50.46(b)(1).