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Category:Graphics incl Charts and Tables
MONTHYEARML23132A2042023-05-12012 May 2023 Annual Radioactive Effluent Release Report SVP-23-022, Correction/Errata for the 2022 Annual Radioactive Effluent Release Report2023-05-12012 May 2023 Correction/Errata for the 2022 Annual Radioactive Effluent Release Report SVPLTR 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 ML15238B6912015-09-0404 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15239B2152015-09-0404 September 2015 Master Report - Tables 1 and 2 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 ML12012A1942012-01-11011 January 2012 SAMG-1 Primary Containment Flooding ML12012A1952012-01-11011 January 2012 SAMG-2 RPV, Containment, and Radioactivity Release Control 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 ML0709304662007-05-24024 May 2007 NRC Receipt of Quad Cities Nuclear Power Station Units 1 & 2, Response to Generic Letter 2003-01, Control Room Habitability (TAC No. MB9845 and MB9846) ML0630406612006-10-30030 October 2006 IR Dresden 2006-010 Attachment 3 RS-06-156, Response to Request for Additional Information Related to Extended Power Uprate Operation Commitments2006-10-17017 October 2006 Response to Request for Additional Information Related to Extended Power Uprate Operation Commitments 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. ML18227D1461976-02-26026 February 1976 Quad-Cities Units 1 & 2 - Submits Table 2, Revised as Supplement C to Quad-Cities Special Report, Which Indicates Latest Core Wide Metal to Water Reaction Percentage of .18 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 2023-05-12
[Table view] Category:Letter type:RS
MONTHYEARRS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval 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 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions 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 RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed 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-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual 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-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion 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-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS 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-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval 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-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request – Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request – Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 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-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program 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-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval 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-23-078, 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-23-059, 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 4b2023-06-0808 June 2023 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 RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 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-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges 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-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location 2024-08-20
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RS-05-123 September 23, 2005 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 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Commitments and Plans Related to Extended Power Uprate Operation
References:
1 . Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S . NRC, "Commitments for Resolution of Steam Dryer Degradation Issue," dated June 27, 2003
- 2. Letter from J. A. Benjamin (Exelon Generation Company, LLC) to U . S. NRC, "Commitments and Information Related to Extended Power Uprate," dated April 2, 2004
- 3. Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S. NRC, "Commitments and Plans Related to Extended Power Uprate Operation,"
dated May 12, 2004 4 . Letter from D. Bost (Exelon Generation Company, LLC) to U. S . NRC, "Commitments and Plans Related to Extended Power Uprate Operation,"
dated December 10, 2004
- 5. Letter from D. Bost (Exelon Generation Company, LLC) to U. S . NRC, "Revised Commitments and Plans Related to Extended Power Uprate Operation," dated January 31, 2005 6 . Letter from J. A. Benjamin (Exelon Generation Company, LLC) to U . S. NRC, "Commitments and Plans Related to Extended Power Uprate Operation,"
dated May 13, 2005
- 7. Letter for P . R. Simpson (Exelon Generation Company, LLC) to U . S. NRC, "Clarification of Regulatory Commitments Related to Extended Power Uprate (EPU) Operations," dated June 13, 2005
September 23, 2005 U. S . Nuclear Regulatory Commission Page 2
- 8. Letter for P. R. Simpson (Exelon Generation Company, LLC) to U . S. NRC, "Commitments and Plans Related to Extended Power Uprate Operation,"
dated July 26, 2005 In the referenced letters, Exelon Generation Company, LLC (EGC) made regulatory commitments regarding operation of Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, at extended power uprate (EPU) conditions. EGC has completed many of the commitments outlined in the referenced letters through engineering evaluations, inspections, equipment modifications, meetings with the NRC, and submittal of various responses to ?4RC requests for additional information and technical documentation .
EGC completed detailed evaluations of the QCNPS replacement steam dryers in accordance with commitments 9 and 10 of Reference 8, and submitted the results of these evaluations to the NRC . On August 29, through September 1, 2005, EGC met the NRC technical staff to discuss the results and conclusions of these evaluations, and the decision and basis regarding scale model testing of the DNPS steam dryers . Prior to meeting adjournment, the NRC technical staff detailed a list of questions that remain to be resolved with respect to evaluation of the QCNPS steam dryers and their suitability for long-term EPU operation . EGC agreed to address these questions to resolve the issue of steam dryer performance for QCNPS . Based on the schedule for completion of analytical work aimed at addressing the remaining questions, EGC is revising the committed dates for meeting with NRC management and submitting a formal request for returning the affected units to EPU operation as outlined in commitments 12 and 13 of Reference 8.
Further, the NRC provided feedback that EGC should provide a justification and basis for continuing EPU operation of the Quad Cities units while the additional engineering work is completed prior to meeting with NRC management . During the technical meeting held on August 29, through September 1, 2005, EGC provided detailed discussions supporting the operation of the QCNPS units at EPU power levels for both short-term (i .e ., prior to meeting with NRC management) and continuous operation . In summary, the detailed evaluations of the QCNPS replacement steam dryers, using the acoustic circuit model and finite element analysis of derived steam dryer loads, demonstrated that adequate structural margin exists for the replacement steam dryers at all operating conditions, up to and including the full licensed power level of 2957 megawatts-thermal (MWt).
Thermal power levels increased throughout the summer, allowing EGC to collect and evaluate data on the QCNPS units at power levels above those included in startup testing following steam dryer replacement. QCNPS Unit 2 collected steam dryer sensor data at 2907 MWt on June 27, 2005, and achieved a maximum power level of 2918 MWt on July 17, 2005 . QCNPS Unit 1 achieved a maximum power level of 2945 MWt on August 10, 2005. EGC evaluated plant and steam dryer performance, including moisture carryover sample results, at these higher levels power and identified no adverse impacts for continued EPU operation . This further validated the acceptable performance of the steam dryers above the original licensed thermal power level (i.e., 2511 MWt) .
In the short term, thermal power levels on the QCNPS units are expected to decrease as condenser backpressure decreases over the coming weeks due to seasonal variations in circulating water temperature . Therefore, the QCNPS units have operated at their maximum
September 23, 2005 U. S . Nuclear Regulatory Commission Page 3 thermal power levels expected for 2005, with no indication of dryer degradation or EPU extent of condition issues .
EGC performed detailed comparisons of in-plant loads, based on data collected from the installed instrumentation, to the loads used to design the replacement steam dryers . EGC assessed the structural adequacy of the replacement steam dryers using strain gauge data collected on the QCNPS Unit 2 steam dryer. Comparisons of this data to calculated stresses, determined using finite element analysis, provided assurance of the robustness of the replacement dryer design . Given the extensive instrumentation installed on the Unit 2 steam dryer, these evaluations also support the conclusion that adequate loads were used in designing the replacement steam dryers . Further, EGC compared strain gauge data collected on the main steam lines of both QCNPS units. In comparing the Unit 1 strain gauge data to that collected on Unit 2, EGC concluded that the steam dryer loads are similar for both units.
In conclusion, the results of comparisons of implant loads to the design loads, the comparisons of main steam line strain gauge data collected on both units, and the evaluation of the installed strain gauge data from the QCNPS Unit 2 steam dryer, provides EGC with additional confidence in the short-term and long-term structural adequacy of the replacement steam dryers to operate at EPU conditions .
The attachment to this letter outlines the remaining committed actions, as well as our going forward commitments that support operation of the DNPS and QCNPS units at EPU conditions .
The commitments contained in the attachment reflect the status of the QCNPS steam dryer replacement effort, including clarification of commitments addressed in Reference 7. The commitments in the attachment supersede those described in the referenced letters, and represent our commitments in their entirety .
If you have any questions concerning this submittal, phase contact Mr . Thomas G. Roddey, at (630) 657-2811 .
Respectfully, Keith R. Jury Director, Licensing and Regulatory Affairs Attachment : Summary of Commitments
ATTACHMENT The following table identifies commitments being made by Exelon Generation Company, LLC (EGC). Any other actions discussed in this letter represent intended or planned actions by EGC. They are described for the NRC's information and are not regulatory commitments.
Committed Date Commitment or Outage 1 EGC will continue to conduct daily monitoring of moisture carryover Ongoing and other key reactor and plant parameters while operating at full power at Dresden Nuclear Power Station (DNPS) Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS) Units 1 and 2, to provide an early indication of potential dryer structural integrity issues . If indications of steam dryer damage or structural integrity concerns are identified, EGC will reduce power at a minimum to the pre-extended power uprate (EPU) level on the affected unit and evaluate and disposition the issue in accordance with the corrective action process.
2 During the next scheduled refueling outage on DNPS Unit 2 and Fall 2005 QCNPS Unit 2, EGC will perform a general visual inspection of the refueling outage reactor pressure vessel internals, steam, and feedwater systems, for DNPS Unit 2 including inspection and disassembly if needed of the most Spring 2006 susceptible components, which include electromatic relief valves .
refueling outage The scope of the inspections will be based upon the results of the for QCNPS EPU vulnerability team effort . If the inspections indicate potential Unit 2 degradation of the reactor pressure vessel internals, steam, or feedwater systems and components, EGC will evaluate and disposition the issue in accordance with the corrective action process. EGC will implement the lessons learned and recommendations from assessment of the vulnerability of other plant equipment to adverse flow effects from EPU operation at DNPS and QCNPS .
3 EGC will attempt to locate and retrieve the lost DNPS Unit 2 Fall 2005 feedwater sample probe . refueling outage for DNPS Unit 2 4 EGC will perform future inspections of the DNPS and QCNPS steam Ongoing dryers using guidance contained in BWRVIP-1 39, "BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines," dated April 2005.
5 EGC will evaluate results of the Fall 2005 DNPS Unit 2 steam dryer Within 30 days of inspection, and determine appropriate action for DNPS Unit 3 . The completing the acceptance criteria will be that no structurally significant cracking is Fall 2005 identified that would limit operation . refueling outage for DNPS Unit 2
ATTACHMENT Committed Date Commitment or Outage 6 EGC will evaluate results of the Spring 2006 QCNPS Unit 2 steam Within 30 days of dryer inspection, and determine appropriate action for QCNPS Unit 1 . completing the The acceptance criteria will be that no structurally significant cracking Spring 2006 is identified that would limit operation . refueling outage for QCNPS Unit 2 7 Where lessons learned from evaluations or inspections conducted Fall 2006 pursuant to commitments described in this letter indicate significant refueling outage potential degradation of the steam dryer, EGC will take appropriate for DNPS Unit 3 actions up to and including shutting down the applicable unit to Spring 2007 conduct inspections or modifications on an expedited basis.
refueling outage for QCNPS Unit 1 8 EGC will meet with the NRC to share the results of the Fall 2005 Within 30 days of DNPS Unit 2 steam dryer inspection, and the impact on, and plans completing the for, DNPS Unit 3. EGC will factor the DNPS Unit 2 inspection results Fall 2005 and analytical work done to date into the decision making process refueling outage related to operating DNPS Unit 3 at EPU power levels and whether a for DNPS Unit 2 appropriate mid-cycle outage is for a steam dryer inspection .
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ATTACHMENT Committed Date Commitment or Outage 9 After replacement of the QCNPS Unit 2 steam dryer, operation at During QCNPS EPU power levels will continue while detailed evaluations of the Unit 2 startup, instrumented data are performed, provided the QCNPS Unit 2 within 14 days of Startup Test Plan acceptance criteria (i.e., go/no-go decisions) are EPU operation, met. Operation will be limited to a power level at which acceptance and within 60 criteria are satisfied . Operational and analytical insights/results will days of QCNPS be shared with the NRC on an ongoing basis during periodic Unit 2 data updates. As a minimum, EGC will provide feedback to the NRC on collection at the steam dryer data and other plant instrumentation data and the 930 MWe or the assessment of the design-basis load cases (i .e., including the maximum reactor acoustic circuit and scale models) during the 24-hour hold point at thermal power 2493 MWt, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of data collection at 930 MWe or the level achieved maximum reactor thermal power level achieved, and within 14 days (Complete) of EPU operation . Detailed evaluations will be performed to compare the predicted QCNPS Unit 2 steam dryer loads, developed using the acoustic circuit model and main steam line strain gauge data, with the actual QCNPS Unit 2 loads obtained from the instrumented steam dryer. EGC will determine whether the assessment of the design-basis load cases at the maximum reactor thermal power level achieved needs to be conducted in a "blind" manner (i .e., similar to the "blind" assessments at lower power levels) and will discuss that determination with the NRC prior to the load determination/blind benchmark . Specific acceptance criteria for the design-basis load cases, including the acoustic circuit and scale models, shall be prepared prior to initiating the assessment of the load cases. The detailed evaluations will be completed and submitted to the NRC within 60 days of data collection at 930 MWe or the maximum reactor thermal power level achieved .
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ATTACHMENT 10 After replacement of the QCNPS Unit 1 steam dryer, operation at During QCNPS EPU power levels will continue while detailed evaluations of the Unit 1 startup QCNPS Unit 2 instrumented data are performed, provided the and within 80 QCNPS Unit 1 Startup Test Plan acceptance criteria (i .e., go/no-go days following decisions) are met. Operation will be limited to a power level at reaching full which acceptance criteria are satisfied. Operational and analytical power on with insights/results will be shared the NRC on an ongoing basis QCNPS Unit 1 during periodic updates. EGC will provide the results of the with the validation of the acoustic circuit model based on QCNPS Unit 2 replacement instrumented steam dryer data prior to exceeding 2511 MWt at steam dryer QCNPS Unit 1 . EGC will also provide feedback to the NRC on the installed plant instrumentation data and calculation of the steam dryer loads (Complete) based on the acoustic circuit model prior to exceeding 2511 MWt and within seven days of reaching the maximum reactor thermal power level achieved . Detailed evaluations will be completed and submitted to the NRC within 80 days following reaching full power on QCNPS Unit 1 with the replacement steam dryer installed.
11 EGC will meet with the NRC technical staff to discuss the results Week of and conclusions of evaluations performed pursuant to commitments August 29, 2005 9 and 10 above. EGC will also discuss the decision and basis (Complete) regarding scale model testing of the DNPS steam dryers during this meeting.
11a EGC will meet with the NRC technical staff to discuss the remaining Week of open items identified pursuant to commitment 11 above. November 7, 2005 12 EGC will meet with NRC management to discuss the results and By November 22, conclusions of evaluations performed pursuant to commitments 9 2005 and 10 above. Where NRC management leading the meeting is not with satisfied the results and conclusions of those evaluations, EGC will voluntarily return the affected QCNPS unit(s) to pre-EPU power levels if EGC is unable to resolve those concerns within 14 days .
13 Following resolution of any concerns identified as pat of December 9, commitment 12, EGC will formally request the return of the affected 2005 unit(s) to EPU operation. Where no concerns are identified under commitment 12, EGC will formally request NRC acceptance for continuous EPU operation of the QCNPS units .
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