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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:Fuel Cycle Reload Report
MONTHYEARSVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 ML22326A0322022-11-17017 November 2022 Core Operating Limits Report for Dresden Unit 3 Cycle 28 SVPLTR 21-0061, Core Operating Limits Report for Dresden Unit 2 Cycle 282021-11-19019 November 2021 Core Operating Limits Report for Dresden Unit 2 Cycle 28 ML20318A0902020-11-0505 November 2020 Core Operating Limits Report for Dresden Unit 3 Cycle 27 ML19322A7522019-11-13013 November 2019 Core Operating Limits Report for Dresden Unit 2 Cycle 27 ML18318A3032018-11-0909 November 2018 Core Operating Limits Report for Unit 3 Cycle 26 ML17320A1232017-11-13013 November 2017 Core Operating Limits Report for Unit 2 Cycle 26 SVPLTR 16-0061, Core Operating Limits Report for Unit 3 Cycle 252016-11-21021 November 2016 Core Operating Limits Report for Unit 3 Cycle 25 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 ML16294A1172016-10-18018 October 2016 Core Operating Limits Report for Dresden Unit 2 Cycle 25 Rev. 1 SVPLTR 16-0056, Cycle 24A Core Operating Limits Report Revision 12016-10-18018 October 2016 Cycle 24A Core Operating Limits Report Revision 1 SVPLTR 15-0070, Core Operating Limits Report for Cycle 24A2015-12-15015 December 2015 Core Operating Limits Report for Cycle 24A SVPLTR 15-0065, Core Operating Limits Report for Cycle 252015-11-16016 November 2015 Core Operating Limits Report for Cycle 25 SVPLTR 15-0059, Core Operating Limits Report, Cycle 242015-10-25025 October 2015 Core Operating Limits Report, Cycle 24 SVPLTR 14-0055, Core Operating Limits Report for Cycle 242014-11-0707 November 2014 Core Operating Limits Report for Cycle 24 SVPLTR 14-0017, Unit, 2 - Transmittal of Core Operating Limits Report for Unit 2 Cycle 242014-03-28028 March 2014 Unit, 2 - Transmittal of Core Operating Limits Report for Unit 2 Cycle 24 SVPLTR 14-0009, Core Operating Report for Cycle 232014-01-31031 January 2014 Core Operating Report for Cycle 23 SVPLTR 13-0047, Core Operating Limits Report for Unit Cycle 242013-11-22022 November 2013 Core Operating Limits Report for Unit Cycle 24 SVPLTR 12-0056, Transmittal of Core Operating Limits Report for Cycle 23, Revision 02012-12-0606 December 2012 Transmittal of Core Operating Limits Report for Cycle 23, Revision 0 SVPLTR 11-0045, Core Operating Limits Report for Unit 2 Cycle 23, Revision 02011-11-11011 November 2011 Core Operating Limits Report for Unit 2 Cycle 23, Revision 0 SVPLTR 11-0038, Core Operating Limits Report for Cycle 22, Revision 12011-10-10010 October 2011 Core Operating Limits Report for Cycle 22, Revision 1 SVPLTR 11-0013, Submittal of Core Operating Limits Report Cycle 22, Revision 22011-03-22022 March 2011 Submittal of Core Operating Limits Report Cycle 22, Revision 2 SVPLTR 10-0048, Core Operating Limits Report for Unit 3 Cycle 22, Revision 02010-11-24024 November 2010 Core Operating Limits Report for Unit 3 Cycle 22, Revision 0 SVPLTR 10-0015, Core Operating Limits Report for Cycle 22, Revision 12010-03-16016 March 2010 Core Operating Limits Report for Cycle 22, Revision 1 SVPLTR 09-0058, Core Operating Limits Report, Cycle 22, Revision 02009-11-25025 November 2009 Core Operating Limits Report, Cycle 22, Revision 0 SVPLTR 08-0063, Core Operating Limits Report for Cycle 21, Revision 02008-11-14014 November 2008 Core Operating Limits Report for Cycle 21, Revision 0 SVPLTR 08-0061, Core Operating Limits Report for Unit 2 Cycle 21, Revision 12008-11-0404 November 2008 Core Operating Limits Report for Unit 2 Cycle 21, Revision 1 SVPLTR 07-0051, Core Operating Limits Report for Unit 2 Cycle 21, Revision 02007-11-0707 November 2007 Core Operating Limits Report for Unit 2 Cycle 21, Revision 0 SVPLTR 07-0047, Core Operating Limits Report for Unit 3 Cycle 20 Revision 12007-10-0101 October 2007 Core Operating Limits Report for Unit 3 Cycle 20 Revision 1 SVPLTR 06-0006, Core Operating Limits Report for Plant Cycle 20 Revision 12006-02-17017 February 2006 Core Operating Limits Report for Plant Cycle 20 Revision 1 SVPLTR 05-0045, Core Operating Limits Report for Unit 2 Cycle 20 Revision 02005-11-29029 November 2005 Core Operating Limits Report for Unit 2 Cycle 20 Revision 0 SVPLTR 05-0029, Core Operating Limits Report for Cycle 19 Revision 22005-07-19019 July 2005 Core Operating Limits Report for Cycle 19 Revision 2 ML0511502892005-04-12012 April 2005 Attachment B, Core Operating Limits Report for Dresden Unit 2 Cycle 19 SVPLTR 04-0080, Letter Transmitting Core Operating Limits Report for Unit 3 Cycle 19 Revision 02004-12-0202 December 2004 Letter Transmitting Core Operating Limits Report for Unit 3 Cycle 19 Revision 0 ML0412805202004-04-30030 April 2004 Core Operating Limits Report for Dresden Unit 3 Cycle 18A - Revision 1 (Non - Proprietary Information) ML0336405852003-12-23023 December 2003 Core Operating Limits Report for Cycle 18A, Revision 0 ML0332301912003-11-0707 November 2003 Attachments C and D - Core Operating Limits Report for Dresden Unit 2 Cycle 19 Revision 0 and Unit 3 Cycle 18 Revision 1, Non-Proprietary Version ML0332301892003-11-0707 November 2003 Core Operating Limits Report for Unit 2 Cycle 19 Revision 0 and Unit 3 Cycle 18 Revision 1 ML0400901502003-10-31031 October 2003 0000-0006-9848-SRLR,Rev. 2 Class I, Supplemental Reload Licensing Report for Dresden Unit 3 Reload 17, Cycle 18 ML0313605732003-05-0909 May 2003 Core Operating Limits Report for Unit 2 Cycle 18, Revision 4 ML0309702932003-03-28028 March 2003 Core Operating Limits Report for Unit 2 Cycle 18, Revision 3 ML0236505462002-12-23023 December 2002 Core Operating Limits Report for Unit 2 Cycle 18, Revision 2 ML0230801052002-10-22022 October 2002 Core Operating Limits Report for Dresden Unit 3 Cycle 18 2023-11-29
[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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Exelon G 4300 Winfield Road Warrenville, IL 60555 www.exeloncorp.com RS-16-206 10 CFR 50.46 October 21, 2016 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), Exelon Generation Company, LLC (EGC) 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. This report covers the period from October 23, 2015, through October 21, 2016.
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.
Res e tfully, Patrick R. Simpson Manager Licensing Attachments:
- 1. Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA5)
- 2. Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA6)
- 3. Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA5)
- 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 Evaluation Model USA5)
PLANT NAME: Dresden Nuclear Power Station, Unit 2 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 10/21/2016 CURRENT OPERATING CYCLE: 25 ANALYSIS OF RECORD Evaluation Model: WCAP-16078-P-A, "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel,"
dated November 2004 Calculations: 1. OPTIMA2-TR021 DR-LOCA, "Dresden 2 & 3 LOCA Analysis for SVEA-96 Optima2 Fuel," Revision 6, dated September 2010
- 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: 1.0/0.8 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 Evaluation Model USA5)
MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 30, 2009 (See Note 1) OPCT = 0°F 10 CFR 50.46 report dated October 29, 2010 (See Note 2) OPCT = 0°F 10 CFR 50.46 report dated October 28, 2011 (See Note 3) OPCT = 0°F 10 CFR 50.46 report dated October 26, 2012 (See Note 4) APCT = 0°F 10 CFR 50.46 report dated October 25, 2013 (See Note 5) OPCT = 0°F 10 CFR 50.46 report dated October 24, 2014 (See Note 6) OPCT = 0°F 10 CFR 50.46 report dated October 23, 2015 (See Note 7) OPCT = 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None; Discharge of fuel related to Note 3 (see Note 8) OPCT = 0°F Total PCT change from current assessments JOPCT = 0°F Cumulative PCT change from current assessments OPCT = 0°F Net PCT 2150°F Page 2 of 2
Attachment 2 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA6)
PLANT NAME: Dresden Nuclear Power Station, Unit 2 ECCS EVALUATION MODEL USA6 REPORT REVISION DATE 10/21/2016 CURRENT OPERATING CYCLE: 25 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-13-68, "Dresden 2 & 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: 1.0/0.8 Double-Ended Guillotine Break in the Recirculation Pump Suction Line Reference Peak Cladding 2150°F Temperature (PCT)
Page 1 of 2
Attachment 2 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA6)
MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS None APCT = 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS New LOCA Model (see Note 8) APCT = 0°F Total PCT change from current assessments JAPCT = 0°F Cumulative PCT change from current assessments Y I APCT = 0°F Net PCT 2150°F Page 2 of 2
Attachment 3 Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA5)
PLANT NAME: Dresden Nuclear Power Station, Unit 3 ECCS EVALUATION MODEL USA5 REPORT REVISION DATE: 10/21/2016 CURRENT OPERATING CYCLE 24 ANALYSIS OF RECORD Evaluation Model: WCAP-16078-P-A, "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," dated November 2004 Calculations: 1. OPTIMA2-TR021 DR-LOCA, "Dresden 2 & 3 LOCA Analysis for SVEA-96 Optima2 Fuel,"
Revision 6, dated September 2010
- 2. NF-BEX-14-77-NP, "Dresden Nuclear Power Station Unit 3 Cycle 24 MAPLHGR Report,"
Revision 0, dated September 2014 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: 1.0/0.8 Double-Ended Guillotine Break in the Recirculation Pump Suction Line Reference Peak Cladding 2150°F Temperature (PCT)
Page 1 of 2
Attachment 3 Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Westinghouse Fuel Evaluation Model USA5)
MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 30, 2009 (See Note 1) APCT = 0°F 10 CFR 50.46 report dated October 29, 2010 (See Note 2) APCT = 0°F 10 CFR 50.46 report dated October 28, 2011 (See Note 3) APCT = 18°F 10 CFR 50.46 report dated October 26, 2012 (See Note 4) APCT = 0°F 10 CFR 50.46 report dated October 25, 2013 (See Note 5) APCT = 0°F 10 CFR 50.46 report dated October 24, 2014 (See Note 6) APCT = 0°F 10 CFR 50.46 report dated October 23, 2015 (See Note 7) APCT = 0°F Net PCT 2168°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 8) APCT = 0°F Total PCT change from current assessments YAPCT = 0°F Cumulative PCT change from current assessments APCT = 0°F Net PCT 2168°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 The referenced letter provided the annual 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems (ECCS) for light-water nuclear power reactors," report for Dresden Nuclear Power Station (DNPS), Units 2 and 3. The letter updated the vessel leakage between the lower shroud and the downcomer. Westinghouse evaluated this change and demonstrated that all 10 CFR 50.46 criteria were satisfied. This evaluation resulted in maximum peak cladding temperature (PCT) impact due to the change in vessel leakage of 2°F for Optima2 fuel with the licensing basis PCT of 2152°F.
This PCT impact will remain in effect until the maximum average planar linear heat generation rate (MAPLHGR) limits for all bundles in future DNPS, Unit 2 and Unit 3 cores are evaluated for this change. The MAPLHGR limits for all bundles in the DNPS, Unit 2 core were evaluated for this change for Cycle 24 and this penalty no longer applies for DNPS, Unit 2. Additionally, the MAPLHGR limits for all bundles in the DNPS, Unit 3 core were evaluated for this change for Cycle 24 and this penalty no longer applies for DNPS, Unit 3.
[
Reference:
Letter from Timothy Hanley (SVPLTR: No. 09-0052, Exelon Generation Company, LLC (EGC)) to NRC, "Plant Specific ECCS Evaluation Changes 10 CFR 50.46 Report," dated October 30, 2009]
- 2. Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for DNPS, Units 2 and 3.
The letter reported the replacement of core spray lower sectional piping in DNPS, Unit 2 during DNPS, Unit 2 Refueling Outage No. 21. Westinghouse evaluated the core spray leakage due to this modification and concluded that the PCT impact was 0°F. The letter also identified a change in input for modeling bypass hole flow coefficient in the Westinghouse LOCA analysis. The impact on PCT due to this change was determined by Westinghouse to be 12°F. Westinghouse established a MAPLHGR limit for the fresh bundles to accommodate the change. For 10 CFR 50.46 reporting purposes, the PCT impact is conservatively applied to all bundle types in the core including the fresh bundles. This PCT update will remain in effect until the MAPLHGR limits for all bundles in future Dresden, Unit 2 and Unit 3 cores are evaluated for the change in bypass hole flow coefficient. The MAPLHGR limits for all bundles in the DNPS, Unit 2 were evaluated for this change for Cycle 24 and this penalty no longer applies for DNPS, Unit 2. Additionally, the MAPLHGR limits for all bundles in the DNPS, Unit 3 core were evaluated for this change for Cycle 24 and this penalty no longer applies for DNPS, Unit 3.
[
Reference:
Letter from Jeffrey Hansen (RS-10-191, EGC) to NRC, "Plant Specific ECCS Evaluation Changes 10 CFR 50.46 Report," dated October 29, 2010]
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Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes
- 3. Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for DNPS, Units 2 and 3.
The letter reported errors in the current Westinghouse Dresden LOCA analysis associated with the use of incorrect R-factors. The impact due to this change was determined to be 18°F in PCT update. For 10 CFR 50.46 reporting purposes, the PCT update is conservatively applied to all bundle types including the fresh bundles. This PCT update will remain in effect only until the MAPLHGR limits for all bundles in future DNPS, Unit 2 and Unit 3 cores are evaluated with the correct R-factors.
[
Reference:
Letter from David M. Gullott (RS-11-171, EGC) to NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated October 28, 2011 ]
- 4. Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for DNPS, Units 2 and 3.
The letter reported no changes, error corrections, or enhancements in the current Westinghouse Dresden LOCA analysis; therefore the delta is 0°F in PCT update.
[
Reference:
Letter from Patrick R. Simpson (RS-12-192, 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 26, 2012]
- 5. Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for DNPS, Units 2 and 3.
The letter reported no changes, error corrections, or enhancements in the current Westinghouse Dresden LOCA analysis; therefore the delta is 0°F in PCT update.
[
Reference:
Letter from Patrick R. Simpson (RS-13-250, 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 25, 2013]
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Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes
- 6. Prior LOCA Model Assessment Updated LOCA/MAPLHGR analyses were performed for DNPS, Unit 2 in support of operating Cycle 24. These analyses maintained the calculated PCT at 2150°F and accounted for the changes to the vessel leakage and bypass hole coefficient. Therefore, the penalties in Notes 1 and 2 no longer apply for DNPS, Unit 2. The penalty for incorrect R-factors in Note 3 remains applicable resulting in a net PCT of 2168"F for DNPS, Unit 2.
No changes, error corrections, or enhancements have been reported for the current DNPS, Unit 3 LOCA analysis. No ECCS-related changes or modifications have occurred at DNPS, Unit 3 that affect the assumptions in the DNPS LOCA analysis of record.
[
Reference:
Letter from Patrick R. Simpson (RS-14-296, 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 24, 2014]
- 7. Prior LOCA Model Assessment Updated LOCA/MAPLHGR analyses were performed for DNPS, Unit 3 in support of Operating Cycle 24. These analyses for DNPS, Unit 3 maintained the calculated PCT at 2150°F and accounted for the changes to the vessel leakage and bypass hole coefficient. Therefore, the previous penalties of 2°F in Note 1 and 12°F in Note 2 above no longer apply for DNPS, Unit 3. The penalties in Attachment 2 listed for Notes 1 & 2 for DNPS, Unit 3 were changed to 0°F. The penalty for incorrect R-factors in Note 3 remains applicable resulting in a net PCT of 2168°F for DNPS, Unit 3.
No changes, error corrections, or enhancements have been reported for the current DNPS, Units 2 and 3 LOCA analyses. No ECCS-related changes or modifications have occurred at DNPS, Units 2 and 3 that affect the assumptions in the DNPS LOCA analysis of record.
[
Reference:
Letter from Patrick R. Simpson (RS-15-265, 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 23, 2015]
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Attachment 4 Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.46 Report Assessment Notes
- 8. Current LOCA Model Assessment The new USA6 LOCA Evaluation Model and calculation has been implemented for 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 and has no additional PCT impacts or estimates as seen in Attachment 2.
Additionally, updated LOCA/MAPLHGR analyses were performed for DNPS, Unit 2 in support of operating Cycle 25. These analyses for DNPS, Unit 2 maintained the calculated PCT at 2150°F and accounted for the incorrect R-factors. Therefore, the previous penalty of 18°F in Note 3 no longer applies for DNPS, Unit 2. The penalty in Attachment 1 listed for Note 3 for DNPS, Unit 2 was changed to 0°F. The penalty for DNPS, Unit 3 in Attachment 3 related to Note 3 remains.
No changes, error corrections, or enhancements have been reported for the current DNPS, Units 2 & 3 LOCA analysis. No ECCS-related changes or modifications have occurred at DNPS, Unit 2 & 3 that affect the assumptions in the DNPS LOCA analysis of record.
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