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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
MONTHYEARIR 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) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, 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 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel 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 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 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 ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 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 SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
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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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