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MONTHYEARSVPLTR 23-0004, Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities2023-02-10010 February 2023 Owner'S Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities ML20280A2482020-10-0707 October 2020 Summary of September 22, 2020, Presubmittal Meeting Between the NRC and Exelon Generation Company LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Units 1 and 2 and Dresden, Units 2 and 3 ML17238A1222017-08-26026 August 2017 Transmittal of Previously Omitted Proposed Technical Specification Page 3.1-2, and Figures 2.1.1, 3.3.1, 3.3.2, 3.5.1, 3.6.1 ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports RS-14-297, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-12-26026 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T RA-13-081, Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term.2013-09-16016 September 2013 Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term. RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites ML12348A2652012-11-27027 November 2012 Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0630406612006-10-30030 October 2006 IR Dresden 2006-010 Attachment 3 ML0617200952006-06-16016 June 2006 Orise - Interim Letter Report for Analytical Results for Four of Eight Water Samples, Batch Four, from the Vicinity of the Dresden Generating Station, Dresden, Illinois (Inspection Report No. 050-00237/2006-007) (Rfta No. 06-001) RS-05-123, Commitments and Plans Related to Extended Power Uprate Operation2005-09-23023 September 2005 Commitments and Plans Related to Extended Power Uprate Operation ML0323407172002-06-0303 June 2002 Outline Submittal for the Dresden Initial Exam - June 2002 ML17252B6271979-05-25025 May 1979 Seismic Evaluation Effort and Analyses Recommendations ML17252B6251979-05-25025 May 1979 Seismic Evaluation Effort and Analyses Recommendations ML17252B0471977-11-30030 November 1977 NEDO-24074 General Electric Boiling Water Reactor Reload-5 Licensing Submittal for Dresden Nuclear Power Station Unit 3. ML17252A4521975-08-14014 August 1975 Report of Abnormal Occurrences Per Section 6.6.A of the Technical Specifications Primary Containment Local Leak-Rate Testing (1975 Refueling Outage) ML17252B0411975-07-28028 July 1975 Summary Report of the Investigatory Work Performed on Dresden 3 Control Rod Drive Collet Housing Cracks ML17252B0511974-08-31031 August 1974 Summary Technical Report of Primary Containment Leak Rate Testing ML17252A9031974-05-23023 May 1974 Letter Reporting a Condition Relating to the Operation of Dresden Nuclear Power Station Unit 3 on 05/15/1974 - Violation of Main Steam Line Area Temperature Detectors ML17252B1821974-03-29029 March 1974 Report No. 29, Supplement B Transient Analysis for Dresden-3 Cycle 3 and Quad-Cities-1 Cycle 2. ML17252A9271974-01-25025 January 1974 Letter Reporting a 01/16/1974 Occurrence Relating to the Failure of Relief Valve 3-203-3A to Operate - Dresden Unit 3 ML17252B1811973-06-20020 June 1973 Special Report No. 29 Transient Analyses for Cycle 2 Using Current Methods. ML17252B0091972-12-0808 December 1972 Letter Reporting a 11/11/1972 Condition Relating to the Discovery of the Main Steam Isolation Valve 3-203B-1B to Have a Closure Time Outside the Technical Specification Limit - Dresden Unit 3 ML17252B1801972-02-22022 February 1972 Supplement to Special Report No. 14, Containment Flammability Control in a Boiling Water Reactor. ML17252B1721971-05-24024 May 1971 Special Report No. 14, Hydrogen Flammability Control System in a Boiling Water Reactor. ML17252B0521970-10-16016 October 1970 Welding Procedure Specification No. P8-P1-GTA-F5-2G 2023-02-10
[Table view] Category:Letter
MONTHYEARML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2152024-09-16016 September 2024 Confirmation of Initial License Examination ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000237/20230052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2024005) ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 ML24215A2912024-08-14014 August 2024 Request for Withholding Information from Public Disclosure Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations 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-24-061, 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-24-063, 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 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 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 ML24183A2752024-05-30030 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 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 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 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 ML24134A1132024-05-0808 May 2024 Retraction: LER 2303-001-00 for Dresden Nuclear Power Station, Unit 2, HPCI Inoperable Due to Air Void Accumulation 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 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 ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release Report 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. 2024-09-06
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{{#Wiki_filter:3645 Warrensvi I le Center Road Cleveland, Ohio 44122 216-991-8841 Woodward-Clyde Consultants May 25, 1979 Mr. K. N. Jabbour Division of Operating Reactors Mail Stop 542 Washington, D.C. 20555
Dear K:
As you requested during our site visit to Milstone in support of the Dresden #2 seismic evaluation effort, I recommend that EGG perform the analysis of three piping systems, recirculation, LPCI suction and seismic example problem #1 identified as being typical of the three methods used to seismically qualified Dresden 2 piping systems. Specifically, I recommend the following analyses be performed: A. Recirculation System 1. Analyze system using best estimate of support stiffness and analysis methods with seismic input from the J. Blume response spectral curves shown in Figure 1 assumed acting first in the nominal N-S and then in the E-W horizontal directions plus 2/3 this spectrum in the vertical direction. Moment resultants are to be combined.on both the SRSS and ABS bases. Resultant seismic stresses to be compared to J. Blume resultant seismic stresses at at least 3 common points. Seismic reaction forces in supports should also be determined and compared to J. Blume results if available. Stress intensification factors of NC 3600 should be used. This effort has essentially been already completed in the summary report by M. E. Nitzel except that the response spectra used as shown in Fig. 1 has been smoothed and ened somewhat from the original Blume curves shown in Fig. 2 and the response spectra has been normalized to a 0.2g ZPGA rather than O.lg QBE ZPGA which was used by Blume. The purpose of this analysis is to evaluate the adequacy and accuracy of the original Blume analysis which is also applicable to steam and feedwater systems. 2. Analyze recirculation system as in (1) above except assume supports are rigid and compare results with J. Blume. 3. Analyze recirculation system using best estimate of support stiffness and using current multi-degree of freedom model and modal analysis methods for the revised EDAC SSE consulting EngineJrQ. response spectral curves shown in Figures 3 and 4 and Environmental Scientists 7 Offices in Other Principal Cities Mr. K. N. Jabbour May 25, 1979 Page 2 Woodward*Clyde Consultants (with torsion-interpolated) for 3 percent damping assumed acting both in the nominal N-S and E-W horizontal directions plus 2/3 of Figure 3 spectrum in the vertical directions. Seismic moment resultants are to be combined on a SRSS basis. Total stresses in the piping system to be determined in accordance with Eq. 9 of NC 3600 for Condition D stress limits. Total reaction forces in the supports should also be determined. Resultant stress or load ratings in the pipe and supports should be compared with Condition D ASME code allowables. In the analysis the stresses and reaction loads induced by deadweight, pressure and seismic should be identified separately. B. LPCI Suction 1. Analyze the LPCI Suction system using seismic coefficient of 0.7g applied statically to the system in the horizontal plane perpendicular to the piping local longitudinal axis. Simultaneously apply a seismic coefficient of 0.067g to the system in the vertical direction. Determine resultant seismic stresses in piping using the stress intensification factors of NC 3600 plus seismic reactions in pipe supports. Assume all supports are rigid. 2. Analyze the LPCI suction system using best estimate of support stiffness and using* current multi-degree of freedom model and modal analysis methods for the revised EDAC SSE (0.2g ZPGA) response spectral curves shown in Figures 5 and 6 (with torsion-interpolated) for 3 percent damping assumed acting both in the nominal N-S and E-W horizontal directions plus 2/3 of the Figure 6 spectrum in the vertical direction. Seismic moment resultants to be combined on a SRSS basis. Total stresses in the piping system to be determined in accordance with Eq. 9 of NC 3600 for ASME Condition D stress limits. Total reaction forces in the supports should also be determined. Resultant stresses or load ratings in the pipe and supports should be compared with Condition D code allowables. In this analysis the stresses and reaction loads induced by deadweight, pressure and seismic should be identified separately. C. Seismic Test Example #1 1. Analyze system in test example 1 shown in Figure 7 attached assuming supports rigid and using current degree of freedom model and modal analysis methods for the revised EDAC SSE (0.2g ZPGA) response spectral curves shown in Fig. 6 (without torsion) for 2 percent damping assumed acting both in the normal N-S and E-W horizontal directions plus 2/3 of the Figure 6 spectrum in the vertical direction.
Mr. K. N. Jabbour May 25, 1979 Page 3 Woodward*Clyde Consultants Seismic moment resultants to be combined on a SRSS basis. Seismic stresses .in the piping system to be determined in accordance with Eq. 9 of NC 3600 for Condition D stress limits. Seismic reaction forces in the supports should also be determined. 2. Repeat the analysis of (1) above assuming (a) vertical supports as not active (b) all supports have a stiffness equal to 10 times the bending stiffness of the pipe spaning between adjacent supports. The analyses described herein will provide quantitative assessment of seismic design margins and thereby should support the qualitative judgement in Chapter 6 of the seismic design adequacy of the Dresden 2 Category I piping systems required for safe shutdown of the RCS and engineered safeguards. I will complete Chapter 6 of the Dresden report assuming that the results of the EGG piping analysis outlined herein will be available as an Appendix to the report which serves to further substanciate the condlusion reached in Chapter 6 that the seismic Category I piping are capable of withstanding SSE seismic loads plus other applicable loads using current analysis and evaluation methods without loss of safety function.
- Please advise if you require any clarification of my dations. Please also note by copy of this letter, I have transmitted this same information to Mr. Saffell of EGG in order to expedite this piping evaluation effort assuming you concur with my recommendation. JDS/ijz Sincerely, ln. Stevenson General Manager cc: Mr. B. c. Saffell, Jr. 1179 Cresent Ave. Idaho Falls, Idaho 83401 H. Levine -NRC l l \ I I ! f 9 l j i I I 11
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