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| {{#Wiki_filter:September 21, 2006Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:September 21, 2006 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIESNUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXELON GENERATION COMPANY, LLC'S EXTENDED POWER UPRATE OPERATION COMMITMENTS (TAC NOS. MD2932 AND MD2933) | | DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXELON GENERATION COMPANY, LLCS EXTENDED POWER UPRATE OPERATION COMMITMENTS (TAC NOS. MD2932 AND MD2933) |
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
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| By letter to the Nuclear Regulatory Commission (NRC) dated January 26, 2006, Exelon made aregulatory commitment to meet with NRC management to discuss the results of evaluationsperformed to support long-term operation of the Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities), at the extended power uprate (EPU) level. The NRC staff is reviewing the modifications installed at Quad Cities and the results of the testsperformed to support EPU operation, and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This request for information was electronically transmitted to your staff on August 24, 2006, and during a discussion with your staff via telephone on September 8, 2006, it was agreed that Exelon would provide a response to these questions by September 30, 2006. After the NRC staff reviews the response, we will schedule a final technical conferencecall with you to discuss the response. Once all technical issues are resolved, the management meeting mentioned above will be scheduled. | | By letter to the Nuclear Regulatory Commission (NRC) dated January 26, 2006, Exelon made a regulatory commitment to meet with NRC management to discuss the results of evaluations performed to support long-term operation of the Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities), at the extended power uprate (EPU) level. |
| C. Crane- 2 -The NRC staff considers that timely responses to requests for additional information helpensure sufficient time is available for staff review and contribute toward the NRC's goal ofefficient and effective use of staff resources. If you should have any questions, please contact John Honcharik at (301) 415-1157.Sincerely,/RA/Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-237, 50-249, 50-254 and 50-265 | | The NRC staff is reviewing the modifications installed at Quad Cities and the results of the tests performed to support EPU operation, and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This request for information was electronically transmitted to your staff on August 24, 2006, and during a discussion with your staff via telephone on September 8, 2006, it was agreed that Exelon would provide a response to these questions by September 30, 2006. After the NRC staff reviews the response, we will schedule a final technical conference call with you to discuss the response. Once all technical issues are resolved, the management meeting mentioned above will be scheduled. |
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| | C. Crane The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If you should have any questions, please contact John Honcharik at (301) 415-1157. |
| | Sincerely, |
| | /RA/ |
| | Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254 and 50-265 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page C. Crane- 3 -The NRC staff considers that timely responses to requests for additional information helpensure sufficient time is available for staff review and contribute toward the NRC's goal ofefficient and effective use of staff resources. If you should have any questions, please contact John Honcharik at (301) 415-1157.Sincerely,/RA/Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-237, 50-249, 50-254 and 50-265
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| | RAI cc w/encl: See next page |
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| | C. Crane The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If you should have any questions, please contact John Honcharik at (301) 415-1157. |
| | Sincerely, |
| | /RA/ |
| | Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254 and 50-265 |
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| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next pageDISTRIBUTION:PUBLICLPL3-2 R/FRidsRgn3MailCenterRidsNrrDorlLpl3-2CWu, NRRRidsNrrLADClarke RidsNrrPMJHoncharikRidsOgcRpTScarbrough, NRR RidsNrrDeEembRidsNrrDciCptbADAMS Accession Number: ML062620149 NRR-106OFFICELPL3-2/PMLPL3-2/LADE/EEMB/BCDCI/CPTB/BCLPL3-2/BCNAMEMBanerjee:mwDClarkeKManolyTLiuDCollinsDATE9/20/069/20/069/20/069/20/069/21/06OFFICIAL RECORD EnclosureREQUEST FOR ADDITIONAL INFORMATIONRELATED TO LONG-TERM EXTENDED POWER UPRATE OPERATION CONDITIONS ATQUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2DOCKET NOS. 50-237 AND 50-249By letter to the Nuclear Regulatory Commission (NRC) dated January 26, 2006, ExelonGeneration Company, LLC (Exelon) made a regulatory commitment to meet with NRC management to discuss the results of evaluations performed to support long-term operation of the Quad Cities Nuclear Power Station, Units 1 and 2 (QC1 and QC2), at the extended poweruprate (EPU) level. The NRC staff has determined that the following information is needed inorder to complete its review:1.How will Exelon monitor the performance of the acoustic side branches (ASBs) installedat QC1 and QC2 in maintaining acceptable main steam line (MSL) pressure fluctuations and vibrations during long-term operation up to extended power uprate (EPU) conditions? For example, what are the plans for monitoring MSL strain gage and accelerometer data; performing plant walkdowns of the ASBs and MSL piping and components; inspecting and testing of MSL components (such as ASBs and electromatic relief valves); and conducting steam dryer inspections? What are the consequences associated with the loss of ASB performance (such as clogging by debris or wear of the wire mesh)? How will ASB performance degradation be addressed?2.What are the sources of new acoustic resonance peaks that appear in the MSL straingage data discussed in Exelon Report AM-2006-002 (Revision 0), "Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Recommendations for Load Reduction," and Exelon Report AM-2006-003 (Revision 0), "Quad Cities Unit 1 Main Steam Line Acoustic Source Identification and Load Reduction," submitted in Exelon letters dated May 3 and August 2, 2006, respectively, following return of the QC units to EPU operation with the ASB modifications? For example, see the resonance peak at 36 Hz in the QC1 MSL strain gage data, and the resonance peaks between 22 and 25 Hz, and at 158 Hz, in QC2 MSL strain gage data. What are the plans to ensure that such peaks do not cause unacceptable pressure loads on the steam dryer and vibrations in MSL components?3.What are the plans to ensure that extended operation of QC1 and QC2 between originallicensed thermal power (OLTP) and EPU conditions will not result in unacceptableacoustic-generated pressure fluctuations and vibrations? For example, see the resonance peaks at 127 and 143 Hz between OLTP and EPU conditions in the Structural Integrity Associates Report SIR-06-199 (May 1, 2006), "Quad Cities Unit 2 Strain Gage and Accelerometer Data Reduction Summary," referenced in Exelon Report AM-2006-002 enclosed with the licensee's submittal dated May 3, 2006. 4.Figures 10 through 13 in Exelon Report AM-2006-002 show the QC2 MSL B vibrationspectra at OLTP and EPU conditions prior to ASB installation for frequencies up to 1 kHz. The figures show harmonics at twice and three times the fundamental singing frequency (about 320 and 480 Hz). What is the potential impact of any new resonances that might be excited at higher frequencies due to the installation of the ASBs?5.In its EPU restart reports submitted on May 3 and August 6, 2006, Exelon does notinclude a revised steam dryer stress analysis for QC1 and QC2 using MSL strain gage data collected during EPU operation with the ASB modifications. As discussed in the past, the NRC staff has not accepted specific aspects of Exelon's steam dryer stress analysis. For example, the bias error and uncertainty assumptions for the acoustic circuit methodology (ACM) are not supported by a comparison of the QC2 steam dryer pressure loads calculated by the ACM during EPU operation before the ASB modifications to actual measured QC2 steam dryer data for specific frequencies intervals or steam dryer locations. Exelon has not justified the assumptions for damping applied in its steam dryer stress analysis in light of the data from the hammer tests of the replacement steam dryers. Also, the bias error/uncertainty assumptions associated with the finite element model stress-to-force transfer functions (based on comparison to dynamic hammer test data on the QC1 and QC2 replacement dryers) needs to be properly addressed. The exponent used by the licensee for the load extrapolation from maximum achieved thermal power to licensed EPU power is not clearly supported by data near the maximum achieved thermal power in the frequency range of interest.
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| Some uncertainties in the steam dryer stress analysis, such as load extrapolation and time shifting, appear more appropriately addressed as bias errors. With the current effectiveness of the ASBs in reducing MSL pressure fluctuations and vibrations to less than OLTP levels prior to the ASB modifications, it is not necessary to resolve these issues with Exelon's steam dryer stress analysis at this time for EPU operation of QC1 and QC2. However, these issues might need to be addressed if the ASB effectiveness becomes degraded at QC1 or QC2, or if Exelon plans to use its steam dryer stress analysis approach, along with its bias error/uncertainty assumptions, for other plants. | | RAI cc w/encl: See next page DISTRIBUTION: |
| | PUBLIC LPL3-2 R/F RidsRgn3MailCenter RidsNrrDorlLpl3-2 CWu, NRR RidsNrrLADClarke RidsNrrPMJHoncharik RidsOgcRp TScarbrough, NRR RidsNrrDeEemb RidsNrrDciCptb ADAMS Accession Number: ML062620149 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA DE/EEMB/BC DCI/CPTB/BC LPL3-2/BC NAME MBanerjee:mw DClarke KManoly TLiu DCollins DATE 9/20/06 9/20/06 9/20/06 9/20/06 9/21/06 OFFICIAL RECORD |
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| | REQUEST FOR ADDITIONAL INFORMATION RELATED TO LONG-TERM EXTENDED POWER UPRATE OPERATION CONDITIONS AT QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-237 AND 50-249 By letter to the Nuclear Regulatory Commission (NRC) dated January 26, 2006, Exelon Generation Company, LLC (Exelon) made a regulatory commitment to meet with NRC management to discuss the results of evaluations performed to support long-term operation of the Quad Cities Nuclear Power Station, Units 1 and 2 (QC1 and QC2), at the extended power uprate (EPU) level. The NRC staff has determined that the following information is needed in order to complete its review: |
| | : 1. How will Exelon monitor the performance of the acoustic side branches (ASBs) installed at QC1 and QC2 in maintaining acceptable main steam line (MSL) pressure fluctuations and vibrations during long-term operation up to extended power uprate (EPU) conditions? For example, what are the plans for monitoring MSL strain gage and accelerometer data; performing plant walkdowns of the ASBs and MSL piping and components; inspecting and testing of MSL components (such as ASBs and electromatic relief valves); and conducting steam dryer inspections? What are the consequences associated with the loss of ASB performance (such as clogging by debris or wear of the wire mesh)? How will ASB performance degradation be addressed? |
| | : 2. What are the sources of new acoustic resonance peaks that appear in the MSL strain gage data discussed in Exelon Report AM-2006-002 (Revision 0), Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Recommendations for Load Reduction, and Exelon Report AM-2006-003 (Revision 0), Quad Cities Unit 1 Main Steam Line Acoustic Source Identification and Load Reduction, submitted in Exelon letters dated May 3 and August 2, 2006, respectively, following return of the QC units to EPU operation with the ASB modifications? For example, see the resonance peak at 36 Hz in the QC1 MSL strain gage data, and the resonance peaks between 22 and 25 Hz, and at 158 Hz, in QC2 MSL strain gage data. What are the plans to ensure that such peaks do not cause unacceptable pressure loads on the steam dryer and vibrations in MSL components? |
| | : 3. What are the plans to ensure that extended operation of QC1 and QC2 between original licensed thermal power (OLTP) and EPU conditions will not result in unacceptable acoustic-generated pressure fluctuations and vibrations? For example, see the resonance peaks at 127 and 143 Hz between OLTP and EPU conditions in the Structural Integrity Associates Report SIR-06-199 (May 1, 2006), Quad Cities Unit 2 Strain Gage and Accelerometer Data Reduction Summary, referenced in Exelon Report AM-2006-002 enclosed with the licensees submittal dated May 3, 2006. |
| | Enclosure |
| | : 4. Figures 10 through 13 in Exelon Report AM-2006-002 show the QC2 MSL B vibration spectra at OLTP and EPU conditions prior to ASB installation for frequencies up to 1 kHz. The figures show harmonics at twice and three times the fundamental singing frequency (about 320 and 480 Hz). What is the potential impact of any new resonances that might be excited at higher frequencies due to the installation of the ASBs? |
| | : 5. In its EPU restart reports submitted on May 3 and August 6, 2006, Exelon does not include a revised steam dryer stress analysis for QC1 and QC2 using MSL strain gage data collected during EPU operation with the ASB modifications. As discussed in the past, the NRC staff has not accepted specific aspects of Exelons steam dryer stress analysis. For example, the bias error and uncertainty assumptions for the acoustic circuit methodology (ACM) are not supported by a comparison of the QC2 steam dryer pressure loads calculated by the ACM during EPU operation before the ASB modifications to actual measured QC2 steam dryer data for specific frequencies intervals or steam dryer locations. Exelon has not justified the assumptions for damping applied in its steam dryer stress analysis in light of the data from the hammer tests of the replacement steam dryers. Also, the bias error/uncertainty assumptions associated with the finite element model stress-to-force transfer functions (based on comparison to dynamic hammer test data on the QC1 and QC2 replacement dryers) needs to be properly addressed. The exponent used by the licensee for the load extrapolation from maximum achieved thermal power to licensed EPU power is not clearly supported by data near the maximum achieved thermal power in the frequency range of interest. |
| | Some uncertainties in the steam dryer stress analysis, such as load extrapolation and time shifting, appear more appropriately addressed as bias errors. With the current effectiveness of the ASBs in reducing MSL pressure fluctuations and vibrations to less than OLTP levels prior to the ASB modifications, it is not necessary to resolve these issues with Exelons steam dryer stress analysis at this time for EPU operation of QC1 and QC2. However, these issues might need to be addressed if the ASB effectiveness becomes degraded at QC1 or QC2, or if Exelon plans to use its steam dryer stress analysis approach, along with its bias error/uncertainty assumptions, for other plants. |
| | |
| | Dresden and Quad Cities Nuclear Power Stations cc: |
| | Site Vice President - Dresden Nuclear Power Station Vice President - Regulatory & Legal Affairs Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9765 Warrenville, IL 60555 Plant Manager - Dresden Nuclear Power Station Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9765 Warrenville, IL 60555 Manager Regulatory Assurance - Dresden Assistant General Counsel Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 200 Exelon Way Morris, IL 60450-9765 Kennett Square, PA 19348 U.S. Nuclear Regulatory Commission Manager Licensing - Dresden & Quad Cities Dresden Resident Inspectors Office Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9766 Warrenville, IL 60555 Chairman Site Vice President - Quad Cities Grundy County Board Exelon Generation Company, LLC Administration Building 22710 206th Avenue N. |
| | 1320 Union Street Cordova, IL 61242-9740 Morris, IL 60450 Plant Manager - Quad Cities Regional Administrator Exelon Generation Company, LLC U.S. NRC, Region III 22710 206th Avenue N. |
| | 801 Warrenville Road Cordova, IL 61242-9740 Lisle, IL 60532-4351 Regulatory Assurance Manager - Quad Cities Illinois Emergency Management Agency Exelon Generation Company, LLC Division of Disaster Assistance & Preparedness 22710 206th Avenue N. |
| | 110 East Adams Street Cordova, IL 61242-9740 Springfield, IL 62701-1109 Quad Cities Resident Inspectors Office Document Control Desk - Licensing U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC 22712 206th Avenue N. |
| | 4300 Winfield Road Cordova, IL 61242 Warrenville, IL 60555 David C. Tubbs Senior Vice President Operations Support MidAmerican Energy Company Exelon Generation Company, LLC One River Center Place 4300 Winfield Road 106 E. Second, P.O. Box 4350 Warrenville, IL 60555 Davenport, IA 52808-4350 |
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| Dresden and Quad Cities Nuclear Power Stations cc: | | Dresden and Quad Cities Nuclear Power Stations cc: |
| Site Vice President - Dresden Nuclear Power StationExelon Generation Company, LLC 6500 N. Dresden Road Morris, IL 60450-9765Plant Manager - Dresden Nuclear Power Station Exelon Generation Company, LLC 6500 N. Dresden Road Morris, IL 60450-9765Manager Regulatory Assurance - DresdenExelon Generation Company, LLC 6500 N. Dresden Road Morris, IL 60450-9765U.S. Nuclear Regulatory CommissionDresden Resident Inspectors Office 6500 N. Dresden Road Morris, IL 60450-9766ChairmanGrundy County Board Administration Building 1320 Union Street Morris, IL 60450Regional AdministratorU.S. NRC, Region III 801 Warrenville RoadLisle, IL 60532-4351Illinois Emergency Management AgencyDivision of Disaster Assistance & Preparedness 110 East Adams Street Springfield, IL 62701-1109Document Control Desk - LicensingExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Senior Vice President Operations SupportExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Vice President - Regulatory & Legal AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Director - Licensing and Regulatory AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Assistant General CounselExelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348Manager Licensing - Dresden & Quad CitiesExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Site Vice President - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
| | Senior Vice President - Midwest Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg. |
| Cordova, IL 61242-9740Plant Manager - Quad CitiesExelon Generation Company, LLC 22710 206th Avenue N.
| | Rock Island, IL 61201}} |
| Cordova, IL 61242-9740Regulatory Assurance Manager - Quad CitiesExelon Generation Company, LLC 22710 206th Avenue N.
| |
| Cordova, IL 61242-9740Quad Cities Resident Inspectors OfficeU.S. Nuclear Regulatory Commission 22712 206th Avenue N.
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| Cordova, IL 61242David C. TubbsMidAmerican Energy Company One River Center Place 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 Dresden and Quad Cities Nuclear Power Stations cc:Senior Vice President - Midwest OperationsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Vice President - Law and Regulatory AffairsMidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808ChairmanRock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
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| Rock Island, IL 61201}} | |
Letter Sequence RAI |
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MONTHYEARML0626201492006-09-21021 September 2006
Request for Additional Information Related to Exelon'S Extended Power Uprate Operation Commitments (TAC Nos. MD2932 & MD2933)
Project stage: RAI
ML0708200122007-03-22022 March 2007
Extended Power Uprate (EPU) Meeting, Handouts from March 22, 2007, Meeting
Project stage: Request
ML0708707282007-04-0404 April 2007
Summary of Meeting with Exelon Generating Company Regarding Resolution of Extended Power Uprate Issues Re Dresden and Quad Cities
Project stage: Meeting
2007-03-22
[Table View] |
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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
ML24183A1082024-08-0808 August 2024
– Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b
SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024
Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities
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
IR 05000254/20243012024-08-0101 August 2024
NRC Initial License Examination Report 05000254/2024301; 05000265/2024301
SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024
Registration of Use of Casks to Store Spent Fuel
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
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
SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024
Regulatory Commitment Change Summary Report
SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024
Registration of Use of Casks to Store Spent Fuel
ML24162A0982024-07-0303 July 2024
– Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 “Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors”
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”
SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024
Registration of Use of Casks to Store Spent Fuel
ML24138A1812024-06-18018 June 2024
Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review
ML24128A2742024-06-14014 June 2024
Notice of Acceptance and Opportunity for Hearing - Letter
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
SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024
Ile Post Exam Package Letter
ML24156A2332024-06-11011 June 2024
Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations
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
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
ML24110A0492024-05-28028 May 2024
Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
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
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
ML24141A2102024-05-20020 May 2024
Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
IR 05000254/20240012024-05-14014 May 2024
Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001
SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024
Annual Radiological Environmental Operating 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
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)
RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024
10 CFR 50.46 Annual Report
ML24109A0662024-05-0202 May 2024
– Relief Request I5R-26, Revision 0
ML24092A3412024-05-0101 May 2024
SLRA - Receipt and Availability - Letter
IR 05000237/20240012024-05-0101 May 2024
Integrated Inspection Report 05000237/2024001 & 05000249/2024001
2024-08-09
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0482024-07-12012 July 2024
Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
ML24135A0182024-05-13013 May 2024
NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment
ML24102A2422024-04-10010 April 2024
NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments
ML24066A1532024-03-0606 March 2024
NRR E-mail Capture - Request for Additional Information TSTF-505, R2, Provide Risk-Informed Extended Completion Times, RITSTF (Risk-Informed Technical Specification Task Force) Initiative 4b and 10 CFR 50.69 License Amendments
ML24066A0872024-03-0404 March 2024
NRR E-mail Capture - Dresden 2 and 3 - Request for Additional Information for Alternative Request I5R-22
ML24067A1242024-03-0101 March 2024
Email to Christian Williams: Request for Additional Information Regarding Dresden Relief Request Dated February 23, 2024
ML24053A1192024-02-22022 February 2024
Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000265/2024010 and 05000254/2024010
ML23349A0362023-12-14014 December 2023
NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability
ML23338A1192023-11-21021 November 2023
NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1
ML23187A0462023-07-0606 July 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004
ML23118A1652023-04-28028 April 2023
NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML23065A2832023-03-0707 March 2023
Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000254/2023010 and 05000265/2023010
ML23052A0652023-02-21021 February 2023
NRR E-mail Capture - Dresden Units 2 and 3 - Request for Additional Information for Alternative Request RV-23H
ML23037A9192023-02-0707 February 2023
Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000237/2023011 and 05000249/2023011
ML23013A1502023-01-17017 January 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2023002
ML23019A0132023-01-12012 January 2023
NRR E-mail Capture - Final RAI Dresden 2 and 3 - License Amendment Pertaining to GNF3 Fuel Transition
ML23004A0262022-12-16016 December 2022
NRR E-mail Capture - Draft Request for Additional Information - Quad Cities Alternative RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves (EPD L-2022-LLR-0070)
ML22348A0452022-12-14014 December 2022
NRR E-mail Capture - Draft Request for Additional Information Regarding Quad Cities Alternative I6R-09
ML22290A0842022-10-13013 October 2022
NRR E-mail Capture - Dresden 2 and 3 - RAI License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies
ML22227A1152022-09-27027 September 2022
Request for Withholding Information from Public Disclosure
ML22270A1032022-09-27027 September 2022
Notification of NRC Baseline Inspection and Request for Information (05000249/2022004)
ML22256A0112022-09-12012 September 2022
NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage
ML22249A2332022-09-0606 September 2022
Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000254/2022011 05000265/2022011
ML22203A0442022-07-21021 July 2022
Request for Additional Information (RAI)
ML22206A0352022-07-13013 July 2022
NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection
ML22199A2422022-07-13013 July 2022
NRR E-mail Capture - Draft RAI Dresden 2 and 3 Proposed Alternative Related to Sblc Nozzle Inspection for the Sixth Inservice Inspection Interval
ML22193A0412022-07-11011 July 2022
NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods
ML22182A1992022-07-0101 July 2022
NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28
ML22178A1362022-06-28028 June 2022
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Quad Cities Station
ML22164A7852022-06-13013 June 2022
NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis
ML22164A8562022-06-13013 June 2022
NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves
ML22164A8582022-06-13013 June 2022
NRR E-mail Capture - RAI Alternative RV-09, MSSVs
ML22076A1122022-03-15015 March 2022
Request for Additional Information Related to the Amendment Request to Transition to GNF3 Fuels (EPID L-2021-LLA-0159) (Redacted)
ML22059A9902022-03-0101 March 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Implement Prime Methodologies for Evaluating Thermal Overpower and Mechanical Overpower Limits for Non-Global Nuclear Fuels Fuel
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22039A1912022-02-0808 February 2022
Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21342A3842021-12-0808 December 2021
NRR E-mail Capture - Request for Additional Information: Quad Cities 1 & 2 License Amendment Request Transition to GNF3 Fuel
ML21294A0032021-10-26026 October 2021
Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding Transition to GNF3 Fuel
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21238A3142021-08-26026 August 2021
Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000254/2021004; 05000265/2021004
ML21244A4012021-08-10010 August 2021
(Final) Request for Information (RAI) Dresden, Units 1, 2, 3, and ISFSI Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50 Appendix E
ML21190A0192021-07-0808 July 2021
NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21097A2602021-04-0808 April 2021
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML21096A1752021-04-0606 April 2021
Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000237/2021011; 05000249/2021011
ML21063A3202021-03-0202 March 2021
RAIs for Dresden, Units 2 and 3, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (EPID L-2020-LLA-0239) (E-mail)
2024-07-12
[Table view] |
Text
September 21, 2006 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXELON GENERATION COMPANY, LLCS EXTENDED POWER UPRATE OPERATION COMMITMENTS (TAC NOS. MD2932 AND MD2933)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated January 26, 2006, Exelon made a regulatory commitment to meet with NRC management to discuss the results of evaluations performed to support long-term operation of the Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities), at the extended power uprate (EPU) level.
The NRC staff is reviewing the modifications installed at Quad Cities and the results of the tests performed to support EPU operation, and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This request for information was electronically transmitted to your staff on August 24, 2006, and during a discussion with your staff via telephone on September 8, 2006, it was agreed that Exelon would provide a response to these questions by September 30, 2006. After the NRC staff reviews the response, we will schedule a final technical conference call with you to discuss the response. Once all technical issues are resolved, the management meeting mentioned above will be scheduled.
C. Crane The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If you should have any questions, please contact John Honcharik at (301) 415-1157.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254 and 50-265
Enclosure:
RAI cc w/encl: See next page
C. Crane The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If you should have any questions, please contact John Honcharik at (301) 415-1157.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254 and 50-265
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsRgn3MailCenter RidsNrrDorlLpl3-2 CWu, NRR RidsNrrLADClarke RidsNrrPMJHoncharik RidsOgcRp TScarbrough, NRR RidsNrrDeEemb RidsNrrDciCptb ADAMS Accession Number: ML062620149 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA DE/EEMB/BC DCI/CPTB/BC LPL3-2/BC NAME MBanerjee:mw DClarke KManoly TLiu DCollins DATE 9/20/06 9/20/06 9/20/06 9/20/06 9/21/06 OFFICIAL RECORD
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LONG-TERM EXTENDED POWER UPRATE OPERATION CONDITIONS AT QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-237 AND 50-249 By letter to the Nuclear Regulatory Commission (NRC) dated January 26, 2006, Exelon Generation Company, LLC (Exelon) made a regulatory commitment to meet with NRC management to discuss the results of evaluations performed to support long-term operation of the Quad Cities Nuclear Power Station, Units 1 and 2 (QC1 and QC2), at the extended power uprate (EPU) level. The NRC staff has determined that the following information is needed in order to complete its review:
- 1. How will Exelon monitor the performance of the acoustic side branches (ASBs) installed at QC1 and QC2 in maintaining acceptable main steam line (MSL) pressure fluctuations and vibrations during long-term operation up to extended power uprate (EPU) conditions? For example, what are the plans for monitoring MSL strain gage and accelerometer data; performing plant walkdowns of the ASBs and MSL piping and components; inspecting and testing of MSL components (such as ASBs and electromatic relief valves); and conducting steam dryer inspections? What are the consequences associated with the loss of ASB performance (such as clogging by debris or wear of the wire mesh)? How will ASB performance degradation be addressed?
- 2. What are the sources of new acoustic resonance peaks that appear in the MSL strain gage data discussed in Exelon Report AM-2006-002 (Revision 0), Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Recommendations for Load Reduction, and Exelon Report AM-2006-003 (Revision 0), Quad Cities Unit 1 Main Steam Line Acoustic Source Identification and Load Reduction, submitted in Exelon letters dated May 3 and August 2, 2006, respectively, following return of the QC units to EPU operation with the ASB modifications? For example, see the resonance peak at 36 Hz in the QC1 MSL strain gage data, and the resonance peaks between 22 and 25 Hz, and at 158 Hz, in QC2 MSL strain gage data. What are the plans to ensure that such peaks do not cause unacceptable pressure loads on the steam dryer and vibrations in MSL components?
- 3. What are the plans to ensure that extended operation of QC1 and QC2 between original licensed thermal power (OLTP) and EPU conditions will not result in unacceptable acoustic-generated pressure fluctuations and vibrations? For example, see the resonance peaks at 127 and 143 Hz between OLTP and EPU conditions in the Structural Integrity Associates Report SIR-06-199 (May 1, 2006), Quad Cities Unit 2 Strain Gage and Accelerometer Data Reduction Summary, referenced in Exelon Report AM-2006-002 enclosed with the licensees submittal dated May 3, 2006.
Enclosure
- 4. Figures 10 through 13 in Exelon Report AM-2006-002 show the QC2 MSL B vibration spectra at OLTP and EPU conditions prior to ASB installation for frequencies up to 1 kHz. The figures show harmonics at twice and three times the fundamental singing frequency (about 320 and 480 Hz). What is the potential impact of any new resonances that might be excited at higher frequencies due to the installation of the ASBs?
- 5. In its EPU restart reports submitted on May 3 and August 6, 2006, Exelon does not include a revised steam dryer stress analysis for QC1 and QC2 using MSL strain gage data collected during EPU operation with the ASB modifications. As discussed in the past, the NRC staff has not accepted specific aspects of Exelons steam dryer stress analysis. For example, the bias error and uncertainty assumptions for the acoustic circuit methodology (ACM) are not supported by a comparison of the QC2 steam dryer pressure loads calculated by the ACM during EPU operation before the ASB modifications to actual measured QC2 steam dryer data for specific frequencies intervals or steam dryer locations. Exelon has not justified the assumptions for damping applied in its steam dryer stress analysis in light of the data from the hammer tests of the replacement steam dryers. Also, the bias error/uncertainty assumptions associated with the finite element model stress-to-force transfer functions (based on comparison to dynamic hammer test data on the QC1 and QC2 replacement dryers) needs to be properly addressed. The exponent used by the licensee for the load extrapolation from maximum achieved thermal power to licensed EPU power is not clearly supported by data near the maximum achieved thermal power in the frequency range of interest.
Some uncertainties in the steam dryer stress analysis, such as load extrapolation and time shifting, appear more appropriately addressed as bias errors. With the current effectiveness of the ASBs in reducing MSL pressure fluctuations and vibrations to less than OLTP levels prior to the ASB modifications, it is not necessary to resolve these issues with Exelons steam dryer stress analysis at this time for EPU operation of QC1 and QC2. However, these issues might need to be addressed if the ASB effectiveness becomes degraded at QC1 or QC2, or if Exelon plans to use its steam dryer stress analysis approach, along with its bias error/uncertainty assumptions, for other plants.
Dresden and Quad Cities Nuclear Power Stations cc:
Site Vice President - Dresden Nuclear Power Station Vice President - Regulatory & Legal Affairs Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9765 Warrenville, IL 60555 Plant Manager - Dresden Nuclear Power Station Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9765 Warrenville, IL 60555 Manager Regulatory Assurance - Dresden Assistant General Counsel Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 200 Exelon Way Morris, IL 60450-9765 Kennett Square, PA 19348 U.S. Nuclear Regulatory Commission Manager Licensing - Dresden & Quad Cities Dresden Resident Inspectors Office Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9766 Warrenville, IL 60555 Chairman Site Vice President - Quad Cities Grundy County Board Exelon Generation Company, LLC Administration Building 22710 206th Avenue N.
1320 Union Street Cordova, IL 61242-9740 Morris, IL 60450 Plant Manager - Quad Cities Regional Administrator Exelon Generation Company, LLC U.S. NRC, Region III 22710 206th Avenue N.
801 Warrenville Road Cordova, IL 61242-9740 Lisle, IL 60532-4351 Regulatory Assurance Manager - Quad Cities Illinois Emergency Management Agency Exelon Generation Company, LLC Division of Disaster Assistance & Preparedness 22710 206th Avenue N.
110 East Adams Street Cordova, IL 61242-9740 Springfield, IL 62701-1109 Quad Cities Resident Inspectors Office Document Control Desk - Licensing U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC 22712 206th Avenue N.
4300 Winfield Road Cordova, IL 61242 Warrenville, IL 60555 David C. Tubbs Senior Vice President Operations Support MidAmerican Energy Company Exelon Generation Company, LLC One River Center Place 4300 Winfield Road 106 E. Second, P.O. Box 4350 Warrenville, IL 60555 Davenport, IA 52808-4350
Dresden and Quad Cities Nuclear Power Stations cc:
Senior Vice President - Midwest Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, IL 61201
