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Category:Annual Operating Report
MONTHYEARML23121A2402023-05-0202 May 2023 Annual Radioactive Effluent Release Report RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-19019 October 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors SVPLTR 21-0027, Radioactive Effluent Release Report and Offsite Dose Calculation Manual2021-04-22022 April 2021 Radioactive Effluent Release Report and Offsite Dose Calculation Manual RS-20-128, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 32020-10-19019 October 2020 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3 RS-19-103, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2019-10-18018 October 2019 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-18-132, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 32018-10-19019 October 2018 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3 SVPLTR 18-0012, Submittal of 2017 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2018-04-24024 April 2018 Submittal of 2017 Radioactive Effluent Release Report and Offsite Dose Calculation Manual RS-17-136, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-10-20020 October 2017 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-206, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-10-21021 October 2016 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report SVPLTR 13-0016, Annual Radiological Environmental Operating Report2013-05-13013 May 2013 Annual Radiological Environmental Operating Report ML13141A6272013-04-30030 April 2013 2012 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 12-0025, 2011 Annual Radiological Environmental Operating Report2012-05-11011 May 2012 2011 Annual Radiological Environmental Operating Report SVPLTR 11-0022, Submittal of 2010 Annual Radiological Environmental Operating Report2011-05-13013 May 2011 Submittal of 2010 Annual Radiological Environmental Operating Report ML11123A0332011-04-29029 April 2011 2010 Annual Radioactive Effluent Release 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 SVPLTR 10-0027, Annual Radiological Environmental Operating Report2010-05-14014 May 2010 Annual Radiological Environmental Operating Report SVPLTR 09-0020, Submittal of 2008 Annual Radiological Environmental Operating Report2009-05-0808 May 2009 Submittal of 2008 Annual Radiological Environmental Operating Report SVPLTR 06-0054, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report2006-11-0909 November 2006 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report ML0414504142004-05-17017 May 2004 Annual Radiological Environmental Operating Report for 2003 ML0314200592003-05-14014 May 2003 Annual Radiological Environmental Operating Report for 2002 ML0037096542000-04-28028 April 2000 Annual Radiological Environmental Operating Report for 1999 2023-05-02
[Table view] Category:Letter type:RS
MONTHYEARRS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-080, 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-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-042, 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H 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-23-003, 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-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request 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-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-101, 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-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 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-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 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-22-049, 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-22-045, 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 RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement 2024-07-31
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4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-22-115 10 CFR 50.46 October 19, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Constellation Energy Generation, LLC (CEG) is submitting this letter and its attachments to meet the annual reporting requirements of the Emergency Core Cooling System (ECCS) Evaluation Model changes and errors for Dresden Nuclear Power Station, Units 2 and 3.
There are no regulatory commitments contained in this letter. If there are any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
Respectfully, Patrick R. Simpson Sr. Manager - Licensing Constellation Energy Generation, LLC Attachments:
- 1. Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel)
- 2. Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Framatome Fuel)
- 3. Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Framatome Fuel)
- 4. Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes
Attachment 1 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel)
PLANT NAME: Dresden Nuclear Power Station, Unit 2 ECCS EVALUATION MODEL: USA6 REPORT REVISION DATE: October 12, 2022 CURRENT OPERATING CYCLE: 28 ANALYSIS OF RECORD Evaluation Model: WCAP-16865-P-A, "Westinghouse BWR ECCS Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application," Revision 1, dated October 2011 Calculations: 1. NF-BEX-13-68P, "Dresden 2 and 3 LOCA Analysis for SVEA-96 Optima2 Fuel," Revision 0, dated June 2015
- 2. NF-BEX-15-101-NP, "Dresden Nuclear Power Station Unit 2, Cycle 25 MAPLHGR Report,"
Revision 0, dated September 2015 Fuel Analyzed in Calculation: SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 Limiting Single Failure: Low Pressure Coolant Injection system injection valve Limiting Break Size and Location: 1.0 Double-Ended Guillotine Break in the Recirculation Pump Suction Line Reference Peak Cladding 2150°F Temperature (PCT)
Page 1 of 2
Attachment 1 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel)
MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 21, 2016 (See Note 1) PCT = 0oF 10 CFR 50.46 report dated October 20, 2017 (See Note 2) PCT = 0oF 10 CFR 50.46 report dated October 19, 2018 (See Note 3) PCT = 0oF 10 CFR 50.46 report dated October 18, 2019 (See Note 4) PCT = 0oF 10 CFR 50.46 report dated October 19, 2020 (See Note 5) PCT = 0oF 10 CFR 50.46 report dated October 19, 2021 (See Note 6) PCT = 0oF Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 7) PCT = 0°F Total PCT change from current assessments PCT = 0°F Cumulative PCT change from current assessments PCT = 0°F Net PCT 2150°F Page 2 of 2
Attachment 2 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Framatome Fuel)
PLANT NAME: Dresden Nuclear Power Station, Unit 2 ECCS EVALUATION MODEL: EXEM BWR-2000 REPORT REVISION DATE: October 12, 2022 CURRENT OPERATING CYCLE: 28 ANALYSIS OF RECORD Evaluation Model: EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model," Revision 0, dated May 2001 Calculations: 1. ANP-3749P, "Dresden Units 2 and 3 ATRIUM 10XM LOCA Break Spectrum Analysis with Increased ADS Flow," Revision 0, dated September 2019
- 2. ANP-3751P, "Dresden Units 2 and 3 ATRIUM 10XM LOCA-ECCS Analysis MAPLHGR Limits with Increased ADS Flow," Revision 0, dated October 2019 Fuel Analyzed in Calculation: ATRIUM 10XM Limiting Fuel Type: ATRIUM 10XM Limiting Single Failure: High Pressure Coolant Injection system Limiting Break Size and Location: 0.13 ft2 Split Break Recirculation Discharge Line Reference Peak Cladding 2101°F Temperature (PCT)
Page 1 of 2
Attachment 2 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Framatome Fuel)
MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 19, 2020 (See Note 5) PCT = -8oF 10 CFR 50.46 report dated October 19, 2021 (See Note 6) PCT = 0°F Net PCT 2093°F B. CURRENT LOCA MODEL ASSESSMENTS Correction of input conversion process for cladding/pellet roughness PCT = 1°F (See Note 7)
Use of pellet temperatures in Rankine vice Fahrenheit (See Note 7) PCT = -1°F Total PCT change from current assessments PCT = 0°F Cumulative PCT change from current assessments PCT = 2°F Net PCT 2093°F Page 2 of 2
Attachment 3 Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Framatome Fuel)
PLANT NAME: Dresden Nuclear Power Station, Unit 3 ECCS EVALUATION MODEL: EXEM BWR-2000 REPORT REVISION DATE: October 12, 2022 CURRENT OPERATING CYCLE: 27 ANALYSIS OF RECORD Evaluation Model: EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model," Revision 0, dated May 2001 Calculations: 1. ANP-3749P, "Dresden Units 2 and 3 ATRIUM 10XM LOCA Break Spectrum Analysis with Increased ADS Flow," Revision 0, dated September 2019
- 2. ANP-3751P, "Dresden Units 2 and 3 ATRIUM 10XM LOCA-ECCS Analysis MAPLHGR Limits with Increased ADS Flow," Revision 0, dated October 2019 Fuel Analyzed in Calculation: ATRIUM 10XM Limiting Fuel Type: ATRIUM 10XM Limiting Single Failure: High Pressure Coolant Injection system Limiting Break Size and Location: 0.13 ft2 Split Break Recirculation Discharge Line Reference Peak Cladding 2101°F Temperature (PCT)
Page 1 of 2
Attachment 3 Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Framatome Fuel)
MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 19, 2021 (See Note 6) PCT = -8oF Net PCT 2093°F B. CURRENT LOCA MODEL ASSESSMENTS Correction of input conversion process for cladding/pellet roughness PCT = 1°F (See Note 7)
Use of pellet temperatures in Rankine vice Fahrenheit (See Note 7) PCT = -1°F Total PCT change from current assessments PCT = 0°F Cumulative PCT change from current assessments PCT = 2°F Net PCT 2093°F Page 2 of 2
Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes Assessment Notes
- 1. Prior Loss of Coolant Accident (LOCA) Model Assessment (2016)
The new USA6 LOCA Evaluation Model and calculation has been implemented for Dresden Nuclear Power Station (DNPS), Unit 2 for all fresh fuel starting with Cycle 25.
This evaluation model and calculation supplement the existing Evaluation Model and calculation. This model reports a limiting PCT of 2150°F.
No changes, error corrections, or enhancements have been reported for the current DNPS, Units 2 and 3 LOCA analysis. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and 3 that affect the assumptions in the DNPS LOCA analysis of record.
[
Reference:
Letter from Patrick R. Simpson (RS-16-206, Exelon Generation Company, LLC (EGC)) to NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3," dated October 21, 2016]
- 2. Prior LOCA Model Assessment (2017)
No changes, error corrections, or enhancements have been reported for the current DNPS, Units 2 and 3 LOCA analysis. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and 3 that affect the assumptions in the DNPS LOCA analysis of record.
[
Reference:
Letter from Patrick R. Simpson (RS-17-136, EGC) to NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3," dated October 20, 2017]
- 3. Prior LOCA Model Assessment (2018)
No changes, error corrections, or enhancements have been reported for the current Westinghouse DNPS, Units 2 and 3 LOCA analysis. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and 3 that affect the assumptions in the DNPS LOCA analyses by Westinghouse and Framatome.
[
Reference:
Letter from Patrick R. Simpson (RS-18-132, EGC) to NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3," dated October 19, 2018.]
Page 1 of 4
Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes
- 4. Prior LOCA Model Assessment (2019)
No changes, error corrections, or enhancements have been reported for the current Westinghouse DNPS, Units 2 and 3 LOCA analyses. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and 3 that affect the assumptions in the DNPS LOCA analyses by Westinghouse.
No ECCS-related changes or modifications occurred at DNPS, Units 2 and 3 that affected the assumptions to any of the LOCA Analyses of Record (AORs).
[
Reference:
Letter from Patrick R. Simpson (RS-19-103, EGC) to NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3," dated October 18, 2019.]
- 5. Prior LOCA Model Assessment (2020)
No changes, error corrections, or enhancements have been reported for the current Westinghouse DNPS, Units 2 and 3 LOCA analysis. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and 3 that affect the assumptions in the DNPS LOCA analyses by Westinghouse and Framatome.
A new Framatome LOCA calculation using the approved EXEM BWR-2000 Evaluation model has been implemented for DNPS Unit 2 for all ATRIUM 10XM fuel loaded into the core. This model reports a limiting PCT of 2101°F. All previous changes, error correction, or enhancements to the Framatome EXEM BWR-2000 Evaluation model that were identified prior to issuance of ANP-3749P and ANP-3751P, both Revision 0, for Unit 2 were addressed in the calculation and no longer applicable.
There are two new changes, error corrections or enhancements in the Framatome EXEM BWR-2000 Evaluation Model for DNPS Units 2. A coding issue was identified in the interpolation process in the RODEX4 Pellet-Cladding Mechanical Interaction routines, which resulted in a +1°F PCT impact. Additionally, some of the RODEX2-2a inputs associated with the fuel geometry were not being appropriately prepared, resulting in a PCT impact of -9°F.
[
Reference:
Letter from Patrick R. Simpson (RS-20-128, EGC) to NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3," dated October 19, 2020.]
Page 2 of 4
Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes
- 6. Prior LOCA Model Assessment (2021)
All fuel evaluated under the Westinghouse USA5 methodology has been removed from operation at Dresden Station and reference to this evaluation model has been removed from the report.
DNPS Unit 2 maintains operation with fuel evaluated under the Westinghouse USA6 evaluation model (fuel loaded fresh in Cycle 25). No changes, error corrections, or enhancements have been reported for the current Westinghouse DNPS, Units 2, LOCA analyses. No ECCS-related changes or modifications have occurred at DNPS, Unit 2, that affect the assumptions in the DNPS LOCA analyses by Westinghouse.
The new Framatome LOCA calculation using the approved EXEM BWR-2000 Evaluation Model has been implemented for DNPS Unit 3 for all ATRIUM 10XM fuel loaded in the core (Cycles 25, 26, and 27). This model was previously implemented for DNPS Unit 2 in November 2019 and included in the previous 2020 LOCA Model Assessment. This model reports a limiting PCT of 2101°F. Prior to implementation of the new calculations on Unit 3, the limiting PCT of 2101°F was adjusted, as was implemented for Unit 2 in the previous 2020 LOCA model assessment, to account for two code issues. The first was a coding issue in the interpolation process in the RODEX4 Pellet-Cladding Mechanical Interaction routines, which resulted in a +1°F PCT impact. The second was that some of the RODEX2-2a inputs (part of AUTOHUP preparation) associated with the fuel geometry were not being appropriately prepared, resulting in a PCT impact of -9°F.
(These adjustments were previously applied to Unit 2; See Note 5)
No changes, error corrections, or enhancements have been reported for the current Framatome DNPS, Units 2, LOCA analyses. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and Unit 3, that affect the assumptions in the DNPS LOCA analyses by Framatome.
[
Reference:
Letter from Patrick R. Simpson (RS-21-110, EGC) to NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3," dated October 19, 2021.]
- 7. Current LOCA Model Assessment DNPS, Unit 2 maintains operation with fuel evaluated under the Westinghouse USA6 evaluation model (fuel loaded fresh in Cycle 25). No changes, error corrections, or enhancements have been reported for the current Westinghouse DNPS, Units 2, LOCA analyses. No ECCS-related changes or modifications have occurred at DNPS, Unit 2, that affect the assumptions in the DNPS LOCA analyses by Westinghouse.
For the Framatome ATRIUM 10XM fuel type, analyzed under the EXEM BWR-2000 evaluation model, two error corrections were identified by Framatome since the last Annual Report. The effects of exposure-dependent thermal conductivity degradation (TCD) are accounted for in the heatup analyses by applying a multiplication factor to the average pellet temperature. A new code was introduced to automate the TCD multiplication factor process. During the code development process, two issues Page 3 of 4
Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes were encountered. (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.
No ECCS-related changes or modifications have occurred at DNPS, Unit 2 and Unit 3, that affect the assumptions in the DNPS LOCA analyses by Framatome.
Page 4 of 4