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Category:Annual Report
MONTHYEARSVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML22320A5592022-11-16016 November 2022 2022 Annual Report - Guarantees of Payment of Deferred Premiums ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums RS-14-296, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-10-24024 October 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors SVPLTR 14-0028, 2013 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2014-04-30030 April 2014 2013 Radioactive Effluent Release Report and Offsite Dose Calculation Manual RS-13-250, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2013-10-25025 October 2013 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-12-192, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 32012-10-26026 October 2012 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Dresden Nuclear Power Station, Units 2 and 3 ML0712101332007-04-27027 April 2007 2006 Annual Radioactive Effluent Release Report ML0632404372006-11-13013 November 2006 Byron Station, Dresden, LaSalle County Station, Peach Bottom Atomic Station, Limerick Station and Quad Cities Nuclear Power Station, 2006 Annual Report - Guarantees of Payment of Deferred Premiums SVPLTR 06-0026, Annual Radiological Environmental Operating Report for 20052006-05-0505 May 2006 Annual Radiological Environmental Operating Report for 2005 SVPLTR 05-0023, Annual Radiological Environmental Operating Report for 20042005-05-13013 May 2005 Annual Radiological Environmental Operating Report for 2004 RS-05-052, Corporation Annual Financial Statements for 20042005-05-0202 May 2005 Corporation Annual Financial Statements for 2004 ML17252B1871969-12-31031 December 1969 1969 Commonwealth Edison Company Annual Report ML17252B1851965-12-31031 December 1965 1965 Annual Report for Commonwealth Edison Company 2023-04-15
[Table view] Category:Letter
MONTHYEARIR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter RS-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 ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, “Safety Limit Mcpr” ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review 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 ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel 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 ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24158A0012024-05-22022 May 2024 License Amendment Request to Adopt TSTF-564 (EPID L-2023-LLA-0120) Illinois State Concurrence ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24135A0722024-05-10010 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report ML24129A1352024-05-0808 May 2024 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, and TSTF-59 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24092A3412024-05-0101 May 2024 SLRA - Receipt and Availability - Letter IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release 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 ML24120A2032024-04-29029 April 2024 Operator Licensing Exam Approval - Dresden Nuclear Power Station, May 2024 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 ML24108A0082024-04-17017 April 2024 Application for Renewed Operating License 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. ML24083A0022024-03-22022 March 2024 IEMA-OHS Comment Dresden HI-STORM Exemption EA & Fonsi SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 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 ML24061A1702024-03-0101 March 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230062024-02-28028 February 2024 Annual Assessment Letter for Dresden Nuclear Station, Units 2 and 3 (Report 05000237/2023006; 05000249/2023006) 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 ML24179A2232024-02-12012 February 2024 ILT 23-1 (2024-301) SVP Letter - 24-007 ILT Exam Submittal IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) 2024-08-09
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- . 1 tio RS-13-250 October 25, 2013 U. S.
Regulatory Commission ArrN: 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 10 CFR 50.46
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 27, 2012, through October 25, 2013. 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.
Respectfu Ily, Patrick R. Simpson Manager -Licensing Exelon Generation Company, LLC Attachments:
- 1. Dresden Nuclear Power Station Unit 2 -10 CFR 50.46 Report (Westinghouse Fuel) 2. Dresden Nuclear Power Station Unit 3 -10 CFR 50.46 Report (Westinghouse Fuel) 3. 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: USA5 REPORT REVISION DATE: 10/3/2013 CURRENT OPERATING CYCLE: 23 ANALYSIS OF RECORD Evaluation Model: "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-16078-P-A, November 2004. Calculations: "Dresden 2 & 3 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TR021 DR-LOCA, Revision 6, Westinghouse Electric Company, LLC. September 2010. Fuel Analyzed in Calculation:
SVEA-960ptima2 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 MARGIN ALLOCATION Attachment 1 Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel) A. PRIOR LOCA MODEL ASSESSMENTS I 10 CFR 50.46 report dated October 30, 2009 (See Note 1) 10 CFR 50.46 report dated October 29, 2010 (See Note 2) 10 CFR 50.46 report dated October 28, 2011 (See Note 3) 10 CFR 50.46 report dated October 26,2012 (See Note 4) Net PCT B. CURRENT LOCA MODEL ASSESSMENTS
= 2°F
= 12°F
= 18°F
= OaF 2182°F None (see Note 5)
= OaF Total PCT change from current assessments
= OaF Cumulative PCT change from current assessments T I = OaF Net PCT Page 2 of 2 Attachment 2 Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Westinghouse Fuel) PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLE: ANALYSIS OF RECORD Evaluation Model: Calculations:
Fuel Analyzed in Calculation:
Limiting Fuel Type: Limiting Single Failure: Limiting Break Size and Location:
Reference Peak Cladding Temperature (PCT) Dresden Nuclear Power Station, Unit 3 USA5 10/3/2013 23 "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-16078-P-A, November 2004. "Dresden 2 & 3 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTI MA2-TR021 DR-LOCA, Revision 6, Westinghouse Electric Company, LLC. September 2010. SVEA-96 Optima2 SVEA-96 Optima2 Low Pressure Coolant Injection system injection valve 1.0 Double-Ended Guillotine Break in the Recirculation Pump Suction Line Page 1 of 2 MARGIN ALLOCATION Attachment 2 Dresden Nuclear Power Station, Unit 3 10 CFR 50.46 Report (Westinghouse Fuel) A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 30, 2009 (See !'Jote 1) 10 CFR 50.46 report dated October 29, 2010 (See Note 2) 10 CFR 50.46 report dated October 28,2011 (See Note 3) 10 CFR 50.46 report dated October 26,2012 (See Note 4) Net PCT B. CURRENT LOCA MODEL ASSESSMENTS None (See !'Jote 5) Total PCT change from current assessments Cumulative PCT change from current assessments Net PCT Page 2 of 2
= 2°F
= 12°F
= 18°F
=OoF 2182°F
=O°F L I = OaF 2182°F Attachment 3 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 update will remain in effect only 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. [
Reference:
Letter from Timothy Hanley (SVPL TR: #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 O°F. The letter also identi'fied 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 only until the MAPLHGR limits for all bundles in future DNPS, Unit 2 and Unit 3 cores are evaluated for the change in bypass hole flow coefficient.
[
Reference:
Letter from Jeffrey Hansen (RS-1 0-191, EGG) to NRC, "Plant Specific ECCS Evaluation Changes -10 CFR 50.46 Report," dated October 29, 2010.] Page 1 of 2 Attachment 3 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 DI\IPS, 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 No new changes, error corrections, or enhancements have been report for the current DNPS LOCA analysis.
No ECCS-related changes or modifications have occurred at DNPS that affect the assumptions in the DNPS LOCA analysis of record. The Analysis of Record was updated to Revision 6, but did not result in a change to the analysis results previously reported.
[
Reference:
Letter from Patrick R. Simpson (RS-12-192, EGC) to NRC, "Plant Specific ECCS Evaluation Changes -10 CFR 50.46 Report," dated October 26, 2012.] 5. Current LOCA Model Assessment 1\10 changes, error corrections, or enhancements have been reported for the current DNPS LOCA analysis.
No ECCS-related changes or modifications have occurred at DNPS that affect the assumptions in the DNPS LOCA analysis of record. Page 2 of 2