Letter Sequence RAI |
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TAC:MB6530, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MB6531, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MB6532, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MB6533, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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MONTHYEARML0414803012004-06-0303 June 2004 Request for Additional Information, Alternative Source Term Amendment Request. TAC Nos. MB6530, MB6531, MB6532, and MB6533 Project stage: RAI ML0416203222004-06-15015 June 2004 Request for Additional Information, Alternative Source Term Amendment Request. TAC Nos. MB6530, MB6531, MB6532, and MB6533 Project stage: RAI RS-04-096, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term2004-06-30030 June 2004 Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term Project stage: Request ML0421201942004-08-19019 August 2004 RAI, Alternative Source Term Amendment Request Project stage: RAI RS-04-143, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term2004-09-22022 September 2004 Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term Project stage: Request ML0505404462005-02-28028 February 2005 2/28/05 - Quad Cities and Dresden Nuclear Power Stations - RAI, Alternative Source Term Amendment Request Project stage: RAI RS-05-020, Quad, Units 1 and 2, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term2005-03-0303 March 2005 Quad, Units 1 and 2, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term Project stage: Request ML0519604062005-07-22022 July 2005 Dresden and Quad Cities - RAI Alternative Source Term Amendment Request Project stage: RAI ML0522301052005-08-11011 August 2005 Forthcoming Meeting with Exelon Generation Company, LLC - Dresden Nuclear Power Station; Quad Cities Nuclear Power Station Project stage: Meeting ML0523100062005-08-19019 August 2005 08/29-30/05, Meeting Notice - Forthcoming Meeting with Exelon Generation Company, LLC - Dresden Nuclear Power Station; Quad Cities Nuclear Power Stations Project stage: Meeting ML0525104372005-09-12012 September 2005 Summary of Meeting on August 29 and 30, 2005, to Discuss the Open Items Related to the NRC Review of Exelon'S Submittal on Alternative Source Term Full Scope License Amendment Project stage: Meeting ML0525203982005-09-16016 September 2005 9/16/05 - Dresden Nuclear Power Station Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 - Alternative Source Term Amendment Request Project stage: Other RS-06-026, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term2006-02-17017 February 2006 Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term Project stage: Request RS-06-085, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term2006-05-25025 May 2006 Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term Project stage: Request ML0620702902006-09-11011 September 2006 License Amendment, Issuance of Amendments Adoption of Alternative Source Term Methodology, MB6530, MB6531, MB6532, MB6533, MC8275, MC8276, MC8277 & MC8278 Project stage: Approval ML0625704832006-09-11011 September 2006 Technical Specifications, Issuance of Amendments Adoption of Alternative Source Term Methodology, MB6530, MB6531, MB6532, MB6533, MC8275, MC8276, MC8277 & MC8278 Project stage: Approval ML0626804042006-09-28028 September 2006 Correction Ltr. to September 11, 2006 AST Amendment Project stage: Acceptance Review 2005-07-22
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Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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)) 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 IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) 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 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 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) 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 ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 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 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 ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 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-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program 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 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 SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23349A0362023-12-14014 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) ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20337A4242020-12-0202 December 2020 Information Request for the Cyber-Security Full Implementation Inspection, Notification to Perform Inspection 05000237/2021401 and 05000249/2021401 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20231A7432020-08-18018 August 2020 Request for Additional Information (IOLB/HFT-RAI-1) Dresden MSIV LAR ML20224A3532020-08-11011 August 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000249/2020004 ML20183A2852020-07-0101 July 2020 Request for Information for an NRC Triennial Baseline Bases Assurance Inspection (Team): Inspection Report 05000254/2020011 and 05000265/2020011 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval 2023-09-21
[Table view] |
Text
July 22, 2005 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 REGARDING ALTERNATIVE SOURCE TERM AMENDMENT REQUEST (TAC NOS. MB6530, MB6531, MB6532, AND MB6533)
Dear Mr. Crane:
By letter dated October 10, 2002, Exelon Generation Company (Exelon) submitted an amendment request to support application of an alternative source term (AST) at Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2.
Our continuing review of the AST amendment request and past request for additional information (RAI) responses in the dose assessment and meteorological areas has resulted in additional questions and need for additional information. These questions are enclosed. These questions were mailed electronically to your staff on June 29, 2005, and could not be discussed with your staff until July 18 and 19, 2005, due to schedule constraints. Please respond to this RAI within 30 days from the date of this letter. A late or incomplete submittal may result in denial of the amendment request under the provisions of 10 CFR 2.108.
Please contact me at 301-415-2277 if your staff has any questions about this RAI.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page
July 22, 2005 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 REGARDING ALTERNATIVE SOURCE TERM AMENDMENT REQUEST (TAC NOS. MB6530, MB6531, MB6532, AND MB6533)
Dear Mr. Crane:
By letter dated October 10, 2002, Exelon Generation Company (Exelon) submitted an amendment request to support application of an alternative source term (AST) at Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2.
Our continuing review of the AST amendment request and past request for additional information (RAI) responses in the dose assessment and meteorological areas has resulted in additional questions and need for additional information. These questions are enclosed. These questions were mailed electronically to your staff on June 29, 2005, and could not be discussed with your staff until July 18 and 19, 2005, due to schedule constraints. Please respond to this RAI within 30 days from the date of this letter. A late or incomplete submittal may result in denial of the amendment request under the provisions of 10 CFR 2.108.
Please contact me at 301-415-2277 if your staff has any questions about this RAI.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsNrrDLpmLpdiii2 (GSuh) RidsRgn3MailCenter RDennig PDIII/2 R/F RidsNrrPMGDick RidsNrrDlpmDpr RidsNrrLAPCoates RidsOgcRp LBrown RidsNrrPMMBanerjee RidsAcrsAcnwMail JHayes ADAMS Accession Number: ML051960406 NRR-088 OFFICE PDIII-2/PM PDIII-2/PM PDIII-2/LA DSSA:SPSB DSSA:SPSB SC:SPSB PDIII-2/SC NAME MBanerejee GDick THarris for LBrown JHayes RDennig GSuh PCoates DATE 07/21/05 07/21/05 07/21/05 07/21/05 07/22/05 07/21/05 07/22/05 OFFICIAL RECORD COPY
Dresden and Quad Cities Nuclear Power Stations cc:
Site Vice President - Dresden Nuclear Power Station Exelon Generation Company, LLC Exelon Generation Company, LLC 4300 Winfield Road 6500 N. Dresden Road Warrenville, IL 60555 Morris, IL 60450-9765 Vice President of Operations - Mid-West Dresden Nuclear Power Station Plant Manager Boiling Water Reactors Exelon Generation Company, LLC Exelon Generation Company, LLC 6500 N. Dresden Road 4300 Winfield Road Morris, IL 60450-9765 Warrenville, IL 60555 Regulatory Assurance Manager - Dresden Vice President - Licensing and Regulatory Exelon Generation Company, LLC Affairs 6500 N. Dresden Road Exelon Generation Company, LLC Morris, IL 60450-9765 4300 Winfield Road Warrenville, IL 60555 U.S. Nuclear Regulatory Commission Dresden Resident Inspectors Office Director - Licensing and Regulatory 6500 N. Dresden Road Affairs Morris, IL 60450-9766 Exelon Generation Company, LLC 4300 Winfield Road Chairman Warrenville, IL 60555 Grundy County Board Administration Building Associate General Counsel 1320 Union Street Exelon Generation Company, LLC Morris, IL 60450 4300 Winfield Road Warrenville, IL 60555 Regional Administrator U.S. NRC, Region III Manager Licensing - Dresden, 801 Warrenville Road Quad Cities and Clinton Lisle, IL 60532-4351 Exelon Generation Company, LLC 4300 Winfield Road Illinois Emergency Management Warrenville, IL 60555 Agency Division of Disaster Assistance & Site Vice President - Quad Cities Nuclear Preparedness Power Station 110 East Adams Street Exelon Generation Company, LLC Springfield, IL 62701-1109 22710 206th Avenue N.
Cordova, IL 61242-9740 Document Control Desk - Licensing Exelon Generation Company, LLC Quad Cities Nuclear Power Station 4300 Winfield Road Plant Manager Warrenville, IL 60555 Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Senior Vice President - Nuclear Services
Dresden and Quad Cities Nuclear Power Stations cc:
Regulatory Assurance Manager - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Resident Inspectors Office U.S. Nuclear Regulatory Commission 22712 206th Avenue N.
Cordova, IL 61242 David C. Tubbs MidAmerican Energy Company One River Center Place 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 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
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION ALTERNATIVE SOURCE TERM AMENDMENT REQUEST The following request for additional information (RAI) is generated from the Nuclear Regulatory Commission staffs continued review of the subject amendment request:
- 1. For the control rod drop accident analysis, the results of the staffs confirmatory analysis do not match Exelon's conclusions. Please provide your calculations. In addition, please discuss the assumptions used for radionuclide deposition and plateout during the period of mechanical vacuum pump operation.
- 2. For the fuel handling accident analysis, the staff's confirmatory analysis does not match Exelon's conclusions. This disparity may be caused by the assumed release rate.
Please confirm that Exelons analysis assumes that the entire activity released from the fuel pool is released to the environment at the end of two hours. Please provide the calculation for the pool decontamination factor.
- 3. For the main steamline break accident analysis, the contributions from noble gases and cesium do not appear to be included in Exelons analysis. Please provide the results of an analysis considering cesium and noble gas contributions. Please provide the assumptions utilized in determining the effect of cesium and noble gases upon dose.
- 4. Loss-of-Coolant Accident (LOCA )
- a. Exelon's analysis assumes credit for radionuclide deposition in vertical main steamline components. It is inappropriate to consider deposition and plateout in such sections of piping. Please provide a revised analysis which does not take credit for vertical removal, or provide a justification for why credit for a vertical run of pipe is appropriate. Please provide Stone & Webster Calculation 086457.022-UR(B)-001, Rev. 0, "Modeling Gravitational Settling/Plateout in Main Steam Lines at Dresden 2 & 3 and Quad Cities 1 & 2," if it is still being used and relied upon in your analysis [sensitive information - redacted].
- b. Please provide the bases for the reduction in the drywell and main steam isolation valve leakage by 50 percent after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, including the applicable reactor pressure vessel and drywell pressures used in this analysis.
- c. For the drawdown time for the standby gas treatment system (SGTS), it is the staffs understanding that the actual performance at Dresden has shown the reactor building at positive pressure for a period of time following the SGTS receiving a start signal. This appears to be contrary to information provided in responses to a previous RAI and to the alternate source term submittal. Please provide information on those occurrences where the reactor building was not at a negative pressure. Provide an analysis which accounts for the reactor building being positive, or provide justification for the staff to conclude that the reactor
building pressure is being maintained negative.
- d. The licensee's analysis assumes a leakage rate of one gallon per minute (gpm) for emergency core cooling system leakage contributions, but it is unclear how this number is supported by plant procedures. Please provide the bases for the assumed leakage rate, including a discussion of applicable plant procedures and surveillance practices which assure that actions are taken to limit actual leakage to one gpm.
- e. The staffs calculations do not result in a decontamination factor of 200 for elemental iodine in the drywell at 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Please provide additional details on the analytical assumptions and initial conditions used in determining the value of 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- 5. With respect to control room dose calculations, Exelon indicated in a response to a previous request for information that operation of the normal control room ventilation system was assumed during all or parts of all accidents. Given that tracer gas inleakage testing was only done for emergency ventilation system operation, please provide information as to how Exelon has confirmed the inleakage characteristics of the control room envelope in the normal operating mode. Please discuss how the system will operate in the event of a loss of offsite power.
- 6. Please discuss whether the control room X/Q values listed in Attachments 2 and 3 to the November 5, 2004, response to an RAI are limiting. Please address whether there are penetrations or other possible release locations that are closer to the control room intake which would result in higher X/Q values and whether factors such as loss of offsite power or single-failure (e.g., loss of forced ventilation) would result in more limiting X/Q values. Page 7 of Attachment 4 states that only one release scenario was considered for each of the design-basis accidents. Please discuss the bounding nature of these scenarios for each design-basis accident.
- 7. Please discuss whether the elevated release X/Q values in Attachments 2 and 3 to the November 5, 2004, letter adequately reflect reduced effective plume heights due to terrain. The PAVAN input files provided as an enclosure to the November 5, 2004, letter, do not include arrays of terrain heights as a function of distance and direction.
Page 2 of the attachment to an October 31, 2003, response to an RAI states that there is a general lack of complexity to the terrain surrounding both sites, but estimates a maximum terrain height of about 25 feet at an unspecified location. Therefore, please provide a table of terrain heights as a function of distance and direction suitable for input into PAVAN. In addition, please discuss the results for downwind sectors with increases in terrain height and whether the resultant X/Q values in those sectors are still lower than the limiting X/Q values presented in Attachments 2 and 3 of the November 5, 2004, letter.
- 8. For purposes of considering the effects of possible downwash in the ARCON96 X/Q calculations, please provide the station chimney diameter(s) and estimated effluent vertical velocities and stack flows during the applicable design-basis accidents.
- 9. Please confirm that the direction from the Dresden control room intake looking toward
the station chimney is approximately 48 degrees from true north (i.e., in a northeasterly direction).
- 10. Please provide a reference citing when Regulatory Guide 1.5 was previously used and reviewed by the staff to estimate the exclusion area boundary and low population zone X/Q values for the main steamline break accident dose assessments.