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Category:Annual Operating Report
MONTHYEARRS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022 CFR50.46 Annual Report RS-21-052, 10 CFR 50.46 Annual Report2021-05-0404 May 2021 10 CFR 50.46 Annual Report RS-20-059, 10 CFR 50.46 Annual Report2020-05-0404 May 2020 10 CFR 50.46 Annual Report SVP-18-029, Submittal of Radioactive Effluent Release Report for 20172018-04-27027 April 2018 Submittal of Radioactive Effluent Release Report for 2017 RS-17-052, Transmittal of 10 CFR 50.46 Annual Report2017-05-0202 May 2017 Transmittal of 10 CFR 50.46 Annual Report RS-16-093, 10 CFR 50.46 Annual Report2016-05-0202 May 2016 10 CFR 50.46 Annual Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report RS-14-142, 10 CFR 50.46 Annual Report2014-05-0202 May 2014 10 CFR 50.46 Annual Report SVP-13-035, Annual Radiological Environmental Operating Report, 1 January Through 31 December 2012, Page 93 of 122 Through End2013-05-31031 May 2013 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2012, Page 93 of 122 Through End ML13135A5832013-05-31031 May 2013 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2012, Cover Through Page 92 of 122 SVP-12-045, Annual Radiological Environmental Operating Report2012-05-11011 May 2012 Annual Radiological Environmental Operating Report RS-12-080, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report2012-05-0404 May 2012 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report ML12123A0192012-04-27027 April 2012 Submittal of Radioactive Effluent Release Report for 2011 SVP-11-042, Annual Radiological Environmental Operating Report2011-05-11011 May 2011 Annual Radiological Environmental Operating Report RS-11-077, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report2011-05-0606 May 2011 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report RS-10-191, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report2010-10-29029 October 2010 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report RS-10-087, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report2010-05-0707 May 2010 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report SVP-09-018, Annual Radiological Environmental Operating Report for 1 January Through 31 December 20082009-05-12012 May 2009 Annual Radiological Environmental Operating Report for 1 January Through 31 December 2008 RS-09-059, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report2009-05-0707 May 2009 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report RS-08-064, CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Annual Report2008-05-0707 May 2008 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Annual Report SVP-07-029, Annual Radiological Environmental Operating Report for 20062007-05-11011 May 2007 Annual Radiological Environmental Operating Report for 2006 SVP-07-001, CFR 50.59/10 CFR 72.48 Summary Report for January 2004 to December 31, 20062007-01-0303 January 2007 CFR 50.59/10 CFR 72.48 Summary Report for January 2004 to December 31, 2006 SVP-05-037, Annual Radiological Environmental Operating Report2005-05-13013 May 2005 Annual Radiological Environmental Operating Report SVP-03-063, Transmittal of 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report for Quad Cities Nuclear Power Station, Units 1 & 22003-05-0808 May 2003 Transmittal of 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report for Quad Cities Nuclear Power Station, Units 1 & 2 2023-05-04
[Table view] Category:Letter type:RS
MONTHYEARRS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023 Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022 Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022 Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station2022-05-25025 May 2022 Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022 CFR50.46 Annual Report RS-22-056, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-054, Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval2022-04-13013 April 2022 Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations 2024-01-03
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Text
4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-22-067 10 CFR 50.46 May 4, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
10 CFR 50.46 Annual Report
Reference:
Letter RS-22-059 from P. R. Simpson (Constellation Energy Generation, LLC) to U.S. NRC, "10 CFR 50.46 Annual Report," dated May 4, 2022 This letter provides the annual report required by 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Ms. Rebecca L. Steinman at (630) 657-2831.
Respectfully, Patrick R. Simpson Sr. Manager Licensing Constellation Energy Generation, LLC Attachments:
- 1. Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Framatome Fuel)
- 2. Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Framatome Fuel)
- 3. Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (GE Hitachi Fuel)
- 4. Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station
ATTACHMENT 1 Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Framatome Fuel) - ATRIUM 10XM PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: EXEM BWR-2000 REPORT REVISION DATE: 05/04/2023 CURRENT OPERATING CYCLE: 28 ANALYSIS OF RECORD Evaluation Model: "EXEM BWR-2000 ECCS Evaluation Model," EMF-2361(P)(A)
Revision 0, May 2021 Calculations: 1. "Quad Cities 1 and 2 ATRIUM 10XM Break Spectrum with Decreased ADS Flow," ANP-3794P, Revision 0, September 2019
- 2. "Quad Cities Units 1 and 2 ATRIUM 10XM LOCA-ECCS Analysis MAPLHGR Limits with Increased ADS Flow," ANP-3795P, Revision 0, October 2019
- 3. "Quad Cities Unit 1 Cycle 27 Reload Safety Analysis,"
ANP-3896P, Revision 0, January 2021 Fuel Analyzed in Calculation: ATRIUM 10XM Limiting Fuel Type: ATRIUM 10XM Limiting Single Failure: High Pressure Coolant Injection Limiting Break Size and Location: 0.12 ft2 split break in the recirculation discharge line Reference Peak Cladding Temperature (PCT): PCT = 2139°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 4, 2021 (See Note 2) PCT = 0°F 10 CFR 50.46 Report dated May 4, 2022 (See Note 3) PCT = 0°F Net PCT 2139°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 4) PCT = 0°F Total PCT change from current assessments PCT = 0°F Cumulative PCT change from current assessments PCT = 0°F Net PCT 2139°F
ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Framatome Fuel) - ATRIUM 10XM PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: EXEM BWR-2000 REPORT REVISION DATE: 05/04/2023 CURRENT OPERATING CYCLE: 27 ANALYSIS OF RECORD Evaluation Model: "EXEM BWR-2000 ECCS Evaluation Model," EMF-2361(P)(A)
Revision 0, May 2021 Calculations: 1. "Quad Cities 1 and 2 ATRIUM 10XM Break Spectrum with Decreased ADS Flow," ANP-3794P, Revision 0, September 2019
- 2. "Quad Cities Units 1 and 2 ATRIUM 10XM LOCA-ECCS Analysis MAPLHGR Limits with Increased ADS Flow," ANP-3795P, Revision 0, October 2019
- 3. "Quad Cities Unit 2 Cycle 27 Reload Safety Analysis,"
ANP-3976P, Revision 0, January 2022 Fuel Analyzed in Calculation: ATRIUM 10XM Limiting Fuel Type: ATRIUM 10XM Limiting Single Failure: High Pressure Coolant Injection Limiting Break Size and Location: 0.12 ft2 split break in the recirculation discharge line Reference Peak Cladding Temperature (PCT): PCT = 2139°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 4, 2020 (See Note 1) PCT = 0°F 10 CFR 50.46 Report dated May 4, 2021 (See Note 2) PCT = 0°F 10 CFR 50.46 Report dated May 4, 2021 (See Note 3) PCT = 0°F Net PCT 2139°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 4) PCT = 0°F Total PCT change from current assessments PCT = 0°F Cumulative PCT change from current assessments PCT = 0°F Net PCT 2139°F
ATTACHMENT 3 Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (GE Hitachi Fuel) - GNF3 PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: SAFER/PRIME REPORT REVISION DATE: 05/04/2023 CURRENT OPERATING CYCLE: 28 ANALYSIS OF RECORD Calculation: "Quad Cities Nuclear Power Station (QCNPS) Units 1 and 2 GNF3 ECCS-LOCA Evaluation," GEH Report 006N1118, Revision 0, July 2022 Fuel Analyzed in Calculation: GNF3 Limiting Fuel Type: GNF3 Limiting Single Failure: Diesel Generator Failure Limiting Break Size and Location: Double-ended guillotine break of recirculation pump suction piping Reference Peak Cladding Temperature (PCT): PCT = 2170°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS No prior LOCA model assessments are applicable since this is PCT = N/A the first time the reference Analysis of Record is being reported (See Note 4)
Net PCT 2170°F B. CURRENT LOCA MODEL ASSESSMENTS Total PCT change from current assessments PCT = N/A Cumulative PCT change from current assessments PCT = N/A Net PCT 2170°F
ATTACHMENT 4 Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes
- 1. Prior Loss-of-Coolant Accident (LOCA) Assessment A new calculation of the Framatome EXEM BWR-2000 Evaluation Model was implemented for QCNPS Unit 2.
There were two assessments to the Framatome EXEM BWR-2000 Evaluation Model that applied to the QCNPS Unit 2 analyses. The first assessment was a coding issue in the RODEX4 thermal-mechanical code interpolation process of the RODEX4 Pellet-Cladding Mechanical Interaction routine with an estimated impact on PCT of +1°F. The second assessment was that some of the RODEX2-2a inputs associated with the fuel rod geometry were not being appropriately prepared with an estimated impact on PCT of -1°F.
Lastly, no ECCS-related changes or modifications occurred at QCNPS Unit 2 that affected the assumptions to any of the LOCA AORs.
[
Reference:
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.
NRC, "10 CFR 50.46 Annual Report," dated May 4, 2020]
- 2. Prior LOCA Assessment A new calculation of the Framatome EXEM BWR-2000 Evaluation Model has been performed for QCNPS Unit 1 with a limiting Peak Clad Temperature of 2139°F. This referenced Peak Clad Temperature is an increase of 40°F from the previously reported referenced Peak Clad Temperature. This calculation incorporates all previous errors and impacts to the LOCA model except for the RODEX2-2a input error discussed in Note 1. The previously discussed impact of 0°F to the limiting Peak Clad Temperature remains valid.
Overall, the implementation of this new calculation along with the one impact represents an increase of the Peak Clad Temperature of +40°F from the previously reported limiting Peak Clad Temperature which is below the l50°Fl threshold for 30 day 10 CFR 50.46 reporting requirements. Implementation of this new calculation supersedes that previously applied and references to the previous calculation are removed from this report.
There were no new changes, error corrections or enhancements to the Framatome EXEM BWR-2000 Evaluation Model for QCNPS Unit 2.
Lastly, no ECCS-related changes or modifications occurred at QCNPS Units 1 and 2 that affected the assumptions to any of the LOCA Analyses of Record (AORs).
[
Reference:
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.
NRC, "10 CFR 50.46 Annual Report," dated May 4, 2021]
- 3. Prior LOCA Assessment There were two new changes to the Framatome EXEM BWR-2000 Evaluation Model for QCNPS Units 1 and 2. The utilization of the RDS2_2_RDX4 code created two changes impacting the effects of exposure-dependent thermal conductivity degradation (TCD) of the EXEM BWR-2000 LOCA methodology.
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ATTACHMENT 4 Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes
- 1. The RDX2_2_RDX4 code corrected the input conversion process for the cladding and pellet roughness values. The assessment showed that the estimated impact on PCT of this RDX2_2_RDX4 coding adjustment is +1°F.
- 2. The calculation of the TCD multiplication factor is based on the ratio of pellet temperatures. As part of the implementation of RDX2_2_RDX4, the process was modified to use pellet temperatures in degrees Rankine instead of degrees Fahrenheit. The assessment showed the estimated impact on PCT of using degrees Rankine to calculate the TCD factor is -1°F.
The overall impact of these changes was 0°F with an absolute value of both changes being 2°F. Lastly, no ECCS-related changes or modifications occurred at QCNPS Units 1 and 2 that affected the assumptions to any of the LOCA AORs.
[
Reference:
Letter from P. R. Simpson (Constellation Energy Generation, LLC) to U.S.
NRC, "10 CFR 50.46 Annual Report," dated May 4, 2022]
- 4. Current LOCA Assessment The new GE Hitachi SAFER/PRIME Evaluation Model and calculation has been implemented for QCNPS Unit 1 for the fresh fuel of GNF3 loaded into the Cycle 28 core.
This model reports a limiting PCT of 2170°F and has no additional PCT impacts or estimates.
It was recently discovered that a change in 2011 was made to the decay heat (DH) input used in nominal calculations for the SAFER evaluation model. The updated DH model is a best estimate decay heat curve based on the 1979 ANS 5.1 standard and considers Service Information Letter (SIL) 636. This change was discovered during review of GNF3 new fuel introduction activities. Additional vendor assessments estimated an impact of 0°F upon GNF2 PCT. This change was already incorporated into the initial GNF3 LOCA evaluation and therefore has no impact on the GNF3 LOCA AOR.
There were no new changes, error corrections or enhancements to the Framatome EXEM BWR-2000 Evaluation Model for QCNPS Units 1 and 2.
Lastly, no ECCS-related changes or modifications occurred at QCNPS Units 1 and 2 that affected the assumptions to any of the LOCA AORs.
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