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Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 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)) 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 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-123, 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 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) 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 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-23-113, 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-23-097, 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 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 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-23-086, 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 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 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- 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 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter 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 ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter 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-23-059, 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 ML23144A3632023-05-26026 May 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 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 ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 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 SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 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 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 ML23013A1502023-01-17017 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2023002 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 ML22227A1152022-09-27027 September 2022 Request for Withholding Information from Public Disclosure 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 ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection 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 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 ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis 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 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 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) ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 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 ML20031C8332020-01-31031 January 2020 NRR E-mail Capture - Request for Additional Information for Quad Cities Request to Revise Technical Specifications to Increase the MSIV Leakage Rate (L-2019-LLA-0045) ML20021A0342020-01-17017 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2020002; 05000265/2020002 ML19134A2792019-05-15015 May 2019 Supplemental Information Needed for Acceptance of License Amendment Request to Increase Main Steam Isolation Valve Allowable Leakage Rates ML18346A4032018-12-0707 December 2018 10 CFR 50.59 (Evaluation of Changes, Tests and Experiments) Inspection Supplemental Request for Information (DRS-A.Shaikh) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17353A9492018-01-0909 January 2018 Supplemental Information Needed for Acceptance of License Amendment Request to Revise Technical Specification Requirements for Secondary Containment ML17355A0112017-12-20020 December 2017 NRR E-mail Capture - Request for Additional Information Regarding Relief Request I5R-11, Revision 2 ML17333A0822017-11-28028 November 2017 17 Quad Cities Nuclear Plant, Unit 2 - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000265/2018001 (DRS-M.Domke) ML17262A0892017-09-19019 September 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies (RS-17-051) ML17198A2292017-07-17017 July 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Set No. 2 (Cac. Nos. MF9675 and MF9676) (RS-17-051) ML17200A0882017-07-0707 July 2017 NRR E-mail Capture - Draft RAI for QC LAR Re Permanent Extension of Type a and Type C Leak Rate Testing Frequencies ML17180A1532017-06-29029 June 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MF9675 and MF9676) (RS-17-051) ML17159A6292017-06-0707 June 2017 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML17072A0012017-02-0909 February 2017 NRR E-mail Capture - Draft RAI for QC LAR Re Loss of Voltage Relay Setting Change 2023-09-21
[Table view] |
Text
February 6, 2006 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SAFETY LIMIT MINIMUM CRITICAL POWER RATIO AMENDMENT REQUEST(TAC NO. MC9243)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated December 15, 2005, Exelon Generation Company, LLC, submitted a request to revise the values of the safety limit minimum critical power ratio in Technical Specification Section 2.1.1, Reactor Core SLs, for Quad Cities Nuclear Power Station, Unit 2.
The NRC staff is reviewing your submittal 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 additional information was e-mailed to your staff, and we held a telephone conference with your staff to discuss the questions on February 1, 2006. It was agreed that you would provide a response by February 10, 2006.
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 circumstances result in the need to revise the requested response date, please contact me at (301) 415-2277.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. Christopher M. Crane, President February 6, 2006 and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SAFETY LIMIT MINIMUM CRITICAL POWER RATIO AMENDMENT REQUEST(TAC NO. MC9243)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated December 15, 2005, Exelon Generation Company, LLC, submitted a request to revise the values of the safety limit minimum critical power ratio in Technical Specification Section 2.1.1, Reactor Core SLs, for Quad Cities Nuclear Power Station, Unit 2.
The NRC staff is reviewing your submittal 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 additional information was e-mailed to your staff, and we held a telephone conference with your staff to discuss the questions on February 1, 2006. It was agreed that you would provide a response by February 10, 2006.
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 circumstances result in the need to revise the requested response date, please contact me at (301) 415-2277.
Sincerely,
/RA/
Maitri Banerjee, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLF R/F RidsNrrDorlLplf RidsNRRPMMBanerjee RidsNrrLADClarke RidsAcrsAcnwMailCenter RidsOGCRp RidsRgn3MailCenter RidsNrrDorlDpr JHoncharik GCranston THuang ADAMS Accession Number: ML060330656 OFFICE LPL3-2/PM LPL3-2/PM LPL3-2/LA SBWB/BC LPL3-2/BC (A)
NAME JHoncharik MBanerjee DClarke GCranston MLandau DATE 2/1/06 2/2/06 2/1/06 2/2/06 2/6/06 OFFICIAL RECORD COPY
Quad Cities Nuclear Power Station Units 1 and 2 cc:
Site Vice President - Quad Cities Nuclear Power Station Exelon Generation Company, LLC Illinois Emergency Management 22710 206th Avenue N. Agency Cordova, IL 61242-9740 Division of Disaster Assistance &
Preparedness Quad Cities Nuclear Power Station Plant Manager 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 Regulatory Assurance Manager - Quad Cities 4300 Winfield Road Exelon Generation Company, LLC Warrenville, IL 60555 22710 206th Avenue N.
Cordova, IL 61242-9740 Senior Vice President of Operations Exelon Generation Company, LLC Quad Cities Resident Inspectors Office 4300 Winfield Road U.S. Nuclear Regulatory Commission Warrenville, IL 60555 22712 206th Avenue N.
Cordova, IL 61242 Vice President - Licensing and Regulatory Affairs David C. Tubbs Exelon Generation Company, LLC MidAmerican Energy Company 4300 Winfield Road One River Center Place Warrenville, IL 60555 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 Director - Licensing and Regulatory Affairs Vice President - Law and Regulatory Affairs Exelon Generation Company, LLC MidAmerican Energy Company 4300 Winfield Road One River Center Place Warrenville, IL 60555 106 E. Second Street P.O. Box 4350 Assistant General Counsel Davenport, IA 52808 Exelon Generation Company, LLC 200 Exelon Way Chairman Kennett Square, PA 19348 Rock Island County Board of Supervisors 1504 3rd Avenue Manager Licensing - Dresden, Quad Cities Rock Island County Office Bldg. and Clinton Rock Island, IL 61201 Exelon Generation Company, LLC 4300 Winfield Road Regional Administrator Warrenville, IL 60555 U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED SAFETY LIMIT MINIMUM CRITICAL POWER RATIO AMENDMENT FOR QUAD CITIES NUCLEAR POWER STATION, UNIT 2 DOCKET NO. 50-265 In reviewing the Exelon Generation Companys (EGCs) submittal dated December 15, 2005, related to a request to revise the values of the safety limit minimum critical power ratio (SLMCPR) in Technical Specification Section 2.1.1, Reactor Core SLs, for the Quad Cities Nuclear Power Station, Unit 2, the NRC staff has determined that the following information is needed in order to complete its review:
- 1. Describe how the Unit 2 Cycle 19 (U2C19) core loading pattern is established for the mixed core configuration as shown in Figure 1 of Attachment 5 with respect to:
a) meeting the cycle energy requirements; b) satisfying all licensing requirements; c) providing adequate thermal margins and operational flexibility; and d) meeting other design and manufacturing criteria established by EGC and Westinghouse.
- 2. On Page 5 of 24 in Attachment 5, clarify that the USAG14 correlation does sufficiently address the Global Nuclear Fuel (GNF) 10 CFR Part 21 issue with respect to Critical Power Determination since the USAG14 correlation was generated based on GEXL14 critical power ratio (CPR) data. If the correlation does not sufficiently address the GNF 10 CFR Part 21 issue, provide the corrective actions including any penalty factor. Also, identify whether the USAG14 correlation was reviewed and approved by the staff, and if not reviewed, provide a copy of the USAG14 for staff review.
- 3. Justify that the adjustment (multiplication) factor in Section 4 of Attachment 5 of the submittal that is applied when using the USAG14 correlation is conservative.
- 4. Provide clarification that the calculated SLMCPR in Table 1 of Attachment 5 for GE14 fuel for Cycle 19 is the same as that in Cycle 18 for dual-loop operation and single-loop operation since the Cycle 19 is an aggressive mixed core operation and the once burned fuel may still dominate.
- 5. It appears that there is no effect on the SLMCPR calculation due to the fuel channel bow. Provide information for mean and standard deviation for both Westinghouse SVEA 96 Optima 2 and GNF GE14 fuel channel bow as shown in Table 2 of Attachment 5 and describe their impact on the Cycle 19 SLMCPR values.
Enclosure
- 6. Describe the process to determine the total core flow uncertainty for dual-loop operation and single-loop operation for Cycle 19 operation and justify that the core flow uncertainty in Section 3 of Attachment 5 of the submittal is conservative for the Cycle 19 SLMCPR calculation, or justify an increase in core flow uncertainty.
- 7. The proposed TS changes involve two sets of SLMCPR for two fuel types from two different vendors. Describe the procedures to apply these two sets of safety limits to the real Cycle 19 operation with respect to display, alarm, monitoring systems and actions taken if the CPR margin is challenged.