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| | number = ML16130A570 | | | number = ML16130A570 |
| | issue date = 05/12/2016 | | | issue date = 05/12/2016 |
| | title = Quad Cities Nuclear Power Station, Units 1 and 2 - Redacted Request for Additional Information Related to License Amendment for Spent Fuel Pool Criticality Methodology for Fuel Channel Bow/Bulge (CAC Nos. MF7160 and MF7161) | | | title = Redacted Request for Additional Information Related to License Amendment for Spent Fuel Pool Criticality Methodology for Fuel Channel Bow/Bulge |
| | author name = Dion J A | | | author name = Dion J |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000254, 05000265 | | | docket = 05000254, 05000265 |
| | license number = DPR-029, DPR-030 | | | license number = DPR-029, DPR-030 |
| | contact person = Dion J A | | | contact person = Dion J |
| | case reference number = CAC MF7160, CAC MF7161 | | | case reference number = CAC MF7160, CAC MF7161 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 5 | | | page count = 5 |
| | project = CAC:MF7160, CAC:MF7161 | | | project = CAC:MF7160, CAC:MF7161 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:PROPRIETARY INFORMATION Mr. Bryan Senior Vice President May 12, 2016 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 12, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) |
| | Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| SUBJECT: QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT FOR SPENT FUEL POOL CRITICALITY METHODOLOGY FOR FUEL CHANNEL BOW/BULGE (CAC NOS. MF7160 AND MF7161) | | ==SUBJECT:== |
| | QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT FOR SPENT FUEL POOL CRITICALITY METHODOLOGY FOR FUEL CHANNEL BOW/BULGE (CAC NOS. MF7160 AND MF7161) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By letter to the U.S. Nuclear Regulatory Commission (NRC) dated December 14, 2015, Exelon Generation Company, LLC submitted a request to amend the Renewed Facility Operating Licenses for for the Quad Cities Nuclear Power Station, Units 1 and 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. As discussed with Mr. Ken Nicely of your staff, a response is expected within 30 days from the date of this letter. Enclosure 1 is a non-proprietary version of the request for additional information (RAI). The RAI transmitted as Enclosure 2 contains proprietary information in accordance with Section 2.390 of Title 10 of the Code of Federal Regulations. When separated from Enclosure 2 this document is decontrolled. The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Enclosure 2 to this letter contains Proprietary Information. Upon separation from Enclosure 2, this letter is DECONTROLLED. PROPRIETARY INFORMATION PROPRIETARY INFORMATION If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1349. Docket Nos. 50-254 and 50-265
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| ===Enclosures:===
| | By letter to the U.S. Nuclear Regulatory Commission (NRC) dated December 14, 2015, Exelon Generation Company, LLC submitted a request to amend the Renewed Facility Operating Licenses for for the Quad Cities Nuclear Power Station, Units 1 and 2. |
| Sincerely,Jeanne A. Dion, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1. Request for Additional Information, non proprietary 2. Request for Additional Information, proprietary cc w/o Enclosure 2: Distribution via Listserv PROPRIETARY INFORMATION PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT REQUEST SPENT FUEL STORAGE POOL CRITICALITY METHODOLOGY FOR FUEL CHANNEL BOW/BULGE EXELON GENERATION COMPANY. LLC QUAD CITIES NUCLEAR POWER STATION. UNITS 1AND2 DOCKET NOS. 50-254 AND 50-265 By application dated December 14, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15348A396), Exelon Generation Company, LLC (the licensee) submitted a license amendment request (LAR) for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2 (Reference 1). The proposed amendment revises the design bases in the updated final safety anaylsis report to reflect the use of a new criticality safety assessment (CSA) fuel channel bow/bulge methodology to support the performance of criticality safety evaluation for ATRIUM-10XM fuel design in the spent fuel pool. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal. Nuclear Performance and Code Review, Division of Safety Systems (SNPB) Background Title 10 of the Code of Federal Regulations (10 CFR), Section 50.68, states, in part, that the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. In your LAR (Reference 1 ), you have provided information from a nuclear criticality safety (NCS) analysis performed for the ATRIUM 10XM fuel design, using a methodology that the NRC has previously approved for QCNPS, Units 1 and 2 (Reference 2), in license amendments Nos. 253 and 248 (respectively). It appears that this information is intended to show that the approved methodology, with necessary modifications to account for the differences between the previously used SVEA-96 Optima2 fuel design and the ATRIUM 10XM fuel design, demonstrates that the Technical Specification 4.3.1.1.c limit is sufficient to ensure compliance with 10 CFR 50.68. The NRC staff has identified some instances where it is not clear if the reactivity impact due to specific conditions was adequately addressed in the NCS analysis. Because the potential reactivity impacts may be positive, the staff requests additional information to verify that the regulatory limit will not be challenged by these potential impacts. Enclosure 1 PROPRIETARY INFORMATION RAl-1: PROPRIETARY INFORMATION -2 -In the LAR (Reference 1 ), the licensee states that no bias or uncertainty needs to be calculated because information from AREVA report FS1-0024092 indicates that fuel geometry changes are not expected to occur for the ATRIUM 1 OXM fuel design at the relatively low burnups being considered. The NRC staff notes that section 4.4 of the AREVA report states that the data presented is intended to provide statistics that will reasonably bound the observed population of channels for each exposure range. The statistics provided for the exposure range of interest does not indicate a non-zero channel bulge/bow. Provide additional detail supporting the statement that fuel geometry changes are not expected to occur. RAl-2: In the LAR (Reference 1), Attachment 3, Table 2, lists the uncertainties and biases calculated for the ATRIUM 10XM, with the intent of demonstrating that the total reactivity effect from all biases and uncertainties for the ATRIUM 1 OXM fuel are bounded by the SVEA-96 Optima2 fuel from the previously approved NCS analysis. A review of the NCS analysis report associated with license amendments Nos. 253 and 248 for QCNPS, Units 1 and 2 (Reference 2), shows a comparable list of uncertainties and biases that were totaled to obtain the total reactivity effect for the SVEA-96 Optima2 fuel. The ATRIUM 10XM data appears to be missing the bias and uncertainty associated with [( ]]. Describe whether the value designated as "ATRIUM 10XM Total Uncertainties and Biases" in this table includes the bias and uncertainty associated with [[ ]], and if not, provide a justification for not including this reactivity effect in Table 2. In the LAR (Reference 1 ), Attachment 3, Table 2, lists the uncertainties and biases calculated for the ATRIUM 1 OXM, with the intent of demonstrating that the total reactivity effect from all biases and uncertainties for the ATRIUM 1 OXM fuel are bounded by the SVEA-96 Optima2 fuel from the previously approved NCS analysis. One of the listed biases is for the "eccentric positioning and fuel assembly channel reactivity effect bias." The NRC staff understands this bias to cover the maximum reactivity increase due to a combination of: (1) eccentric positioning and (2) whether the fuel assembly is channeled or not. Confirm the staff's understanding, or provide clarification as to the intent of this bias. References: 1. "Quad Cities, Units 1 and 2 -Request for License Amendment Regarding Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge." Dated December 14, 2015, ADAMS Accession No. ML 15348A396. 2. NRC Letter to TVA, Dated December 31, 2014 "Quad Cities Nuclear Power Station, Units 1 and 2-Issuance of Amendments Regarding NETCO Inserts (TAC. NOS. MF2489 AND MF2490)(RS-13-148), ADAMS Accession No. ML 14346A306. OFFICIAL US& ONLY PROPRIETARY INFORMATION PROPRIETARY INFORMATION If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1349. Docket Nos. 50-254 and 50-265
| | 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. As discussed with Mr. Ken Nicely of your staff, a response is expected within 30 days from the date of this letter. |
| | Enclosure 1 is a non-proprietary version of the request for additional information (RAI). The RAI transmitted as Enclosure 2 contains proprietary information in accordance with Section 2.390 of Title 10 of the Code of Federal Regulations. When separated from Enclosure 2 this document is decontrolled. |
| | The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. |
| | Enclosure 2 to this letter contains Proprietary Information. Upon separation from Enclosure 2, this letter is DECONTROLLED. |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION |
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| ===Enclosures:=== | | OFFICIAL USE ONLY PROPRIETARY INFORMATION B. Hanson If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1349. |
| Sincerely,IRA! Jeanne A Dion, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1. Request for Additional Information, non proprietary 2. Request for Additional Information, proprietary cc w/o Enclosure 2: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-2 R/F RidsNrrLASRohrer Resource RidsAcrs_MailCTR Resource RidsNrrPMQuadCities Resource ADAMS Accession Nos. Proprietary ML 16130A572 OFFICE DORULPL3-2/PM DORL/LPL3-2/LA NAME JDion SRohrer DATE 5/11/16 5/9/16 RidsNrrDorllpl3-2 Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource Non-Proprietary ML 16130A570 *via E-mail DORL/LPL3-2/B (A)* DORL/LPL3-2/PM EMiller JDion 5/12/16 5/12/16 OFFICIAL AGENCY COPY PROPRIETARY INFORMATION}} | | Sincerely, fk-_t*~ |
| | Jeanne A. Dion, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 |
| | |
| | ==Enclosures:== |
| | : 1. Request for Additional Information, non proprietary |
| | : 2. Request for Additional Information, proprietary cc w/o Enclosure 2: |
| | Distribution via Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT REQUEST SPENT FUEL STORAGE POOL CRITICALITY METHODOLOGY FOR FUEL CHANNEL BOW/BULGE EXELON GENERATION COMPANY. LLC QUAD CITIES NUCLEAR POWER STATION. UNITS 1AND2 DOCKET NOS. 50-254 AND 50-265 By application dated December 14, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15348A396), Exelon Generation Company, LLC (the licensee) submitted a license amendment request (LAR) for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2 (Reference 1). The proposed amendment revises the design bases in the updated final safety anaylsis report to reflect the use of a new criticality safety assessment (CSA) fuel channel bow/bulge methodology to support the performance of criticality safety evaluation for ATRIUM-10XM fuel design in the spent fuel pool. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal. |
| | Nuclear Performance and Code Review, Division of Safety Systems (SNPB) |
| | |
| | ===Background=== |
| | Title 10 of the Code of Federal Regulations (10 CFR), Section 50.68, states, in part, that the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. In your LAR (Reference 1), you have provided information from a nuclear criticality safety (NCS) analysis performed for the ATRIUM 10XM fuel design, using a methodology that the NRC has previously approved for QCNPS, Units 1 and 2 (Reference 2), in license amendments Nos. 253 and 248 (respectively). It appears that this information is intended to show that the approved methodology, with necessary modifications to account for the differences between the previously used SVEA-96 Optima2 fuel design and the ATRIUM 10XM fuel design, demonstrates that the Technical Specification 4.3.1.1.c limit is sufficient to ensure compliance with 10 CFR 50.68. The NRC staff has identified some instances where it is not clear if the reactivity impact due to specific conditions was adequately addressed in the NCS analysis. Because the potential reactivity impacts may be positive, the staff requests additional information to verify that the regulatory limit will not be challenged by these potential impacts. |
| | Enclosure 1 OFFICIAL USE ONLY PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION RAl-1: |
| | In the LAR (Reference 1), the licensee states that no bias or uncertainty needs to be calculated because information from AREVA report FS1-0024092 indicates that fuel geometry changes are not expected to occur for the ATRIUM 1OXM fuel design at the relatively low burnups being considered. The NRC staff notes that section 4.4 of the AREVA report states that the data presented is intended to provide statistics that will reasonably bound the observed population of channels for each exposure range. The statistics provided for the exposure range of interest does not indicate a non-zero channel bulge/bow. Provide additional detail supporting the statement that fuel geometry changes are not expected to occur. |
| | RAl-2: |
| | In the LAR (Reference 1), Attachment 3, Table 2, lists the uncertainties and biases calculated for the ATRIUM 10XM, with the intent of demonstrating that the total reactivity effect from all biases and uncertainties for the ATRIUM 1OXM fuel are bounded by the SVEA-96 Optima2 fuel from the previously approved NCS analysis. A review of the NCS analysis report associated with license amendments Nos. 253 and 248 for QCNPS, Units 1 and 2 (Reference 2), shows a comparable list of uncertainties and biases that were totaled to obtain the total reactivity effect for the SVEA-96 Optima2 fuel. The ATRIUM 10XM data appears to be missing the bias and uncertainty associated with [( )). Describe whether the value designated as "ATRIUM 10XM Total Uncertainties and Biases" in this table includes the bias and uncertainty associated with (( )), and if not, provide a justification for not including this reactivity effect in Table 2. |
| | In the LAR (Reference 1), Attachment 3, Table 2, lists the uncertainties and biases calculated for the ATRIUM 1OXM, with the intent of demonstrating that the total reactivity effect from all biases and uncertainties for the ATRIUM 1OXM fuel are bounded by the SVEA-96 Optima2 fuel from the previously approved NCS analysis. One of the listed biases is for the "eccentric positioning and fuel assembly channel reactivity effect bias." The NRC staff understands this bias to cover the maximum reactivity increase due to a combination of: (1) eccentric positioning and (2) whether the fuel assembly is channeled or not. Confirm the staff's understanding, or provide clarification as to the intent of this bias. |
| | |
| | ==References:== |
| | : 1. "Quad Cities, Units 1 and 2 - Request for License Amendment Regarding Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge." Dated December 14, 2015, ADAMS Accession No. ML15348A396. |
| | : 2. NRC Letter to TVA, Dated December 31, 2014 "Quad Cities Nuclear Power Station, Units 1 and 2- Issuance of Amendments Regarding NETCO Inserts (TAC. NOS. |
| | MF2489 AND MF2490)(RS-13-148), ADAMS Accession No. ML14346A306. |
| | OFFICIAL US& ONLY PROPRIETARY INFORMATION |
| | |
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION B. Hanson If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1349. |
| | Sincerely, IRA! |
| | Jeanne A Dion, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 |
| | |
| | ==Enclosures:== |
| | : 1. Request for Additional Information, non proprietary |
| | : 2. Request for Additional Information, proprietary cc w/o Enclosure 2: |
| | Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPL3-2 R/F RidsNrrDorllpl3-2 Resource RidsNrrLASRohrer Resource RidsRgn3MailCenter Resource RidsAcrs_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrPMQuadCities Resource ADAMS Accession Nos. Proprietary ML16130A572 Non-Proprietary ML16130A570 |
| | *via E-mail OFFICE DORULPL3-2/PM DORL/LPL3-2/LA DORL/LPL3-2/B (A)* DORL/LPL3-2/PM NAME JDion SRohrer EMiller JDion DATE 5/11/16 5/9/16 5/12/16 5/12/16 OFFICIAL AGENCY COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION}} |
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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
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OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 12, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT FOR SPENT FUEL POOL CRITICALITY METHODOLOGY FOR FUEL CHANNEL BOW/BULGE (CAC NOS. MF7160 AND MF7161)
Dear Mr. Hanson:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated December 14, 2015, Exelon Generation Company, LLC submitted a request to amend the Renewed Facility Operating Licenses for for the Quad Cities Nuclear Power Station, Units 1 and 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. As discussed with Mr. Ken Nicely of your staff, a response is expected within 30 days from the date of this letter.
Enclosure 1 is a non-proprietary version of the request for additional information (RAI). The RAI transmitted as Enclosure 2 contains proprietary information in accordance with Section 2.390 of Title 10 of the Code of Federal Regulations. When separated from Enclosure 2 this document is decontrolled.
The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
Enclosure 2 to this letter contains Proprietary Information. Upon separation from Enclosure 2, this letter is DECONTROLLED.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION B. Hanson If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1349.
Sincerely, fk-_t*~
Jeanne A. Dion, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosures:
- 1. Request for Additional Information, non proprietary
- 2. Request for Additional Information, proprietary cc w/o Enclosure 2:
Distribution via Listserv OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT REQUEST SPENT FUEL STORAGE POOL CRITICALITY METHODOLOGY FOR FUEL CHANNEL BOW/BULGE EXELON GENERATION COMPANY. LLC QUAD CITIES NUCLEAR POWER STATION. UNITS 1AND2 DOCKET NOS. 50-254 AND 50-265 By application dated December 14, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15348A396), Exelon Generation Company, LLC (the licensee) submitted a license amendment request (LAR) for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2 (Reference 1). The proposed amendment revises the design bases in the updated final safety anaylsis report to reflect the use of a new criticality safety assessment (CSA) fuel channel bow/bulge methodology to support the performance of criticality safety evaluation for ATRIUM-10XM fuel design in the spent fuel pool.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
Nuclear Performance and Code Review, Division of Safety Systems (SNPB)
Background
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.68, states, in part, that the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. In your LAR (Reference 1), you have provided information from a nuclear criticality safety (NCS) analysis performed for the ATRIUM 10XM fuel design, using a methodology that the NRC has previously approved for QCNPS, Units 1 and 2 (Reference 2), in license amendments Nos. 253 and 248 (respectively). It appears that this information is intended to show that the approved methodology, with necessary modifications to account for the differences between the previously used SVEA-96 Optima2 fuel design and the ATRIUM 10XM fuel design, demonstrates that the Technical Specification 4.3.1.1.c limit is sufficient to ensure compliance with 10 CFR 50.68. The NRC staff has identified some instances where it is not clear if the reactivity impact due to specific conditions was adequately addressed in the NCS analysis. Because the potential reactivity impacts may be positive, the staff requests additional information to verify that the regulatory limit will not be challenged by these potential impacts.
Enclosure 1 OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION RAl-1:
In the LAR (Reference 1), the licensee states that no bias or uncertainty needs to be calculated because information from AREVA report FS1-0024092 indicates that fuel geometry changes are not expected to occur for the ATRIUM 1OXM fuel design at the relatively low burnups being considered. The NRC staff notes that section 4.4 of the AREVA report states that the data presented is intended to provide statistics that will reasonably bound the observed population of channels for each exposure range. The statistics provided for the exposure range of interest does not indicate a non-zero channel bulge/bow. Provide additional detail supporting the statement that fuel geometry changes are not expected to occur.
RAl-2:
In the LAR (Reference 1), Attachment 3, Table 2, lists the uncertainties and biases calculated for the ATRIUM 10XM, with the intent of demonstrating that the total reactivity effect from all biases and uncertainties for the ATRIUM 1OXM fuel are bounded by the SVEA-96 Optima2 fuel from the previously approved NCS analysis. A review of the NCS analysis report associated with license amendments Nos. 253 and 248 for QCNPS, Units 1 and 2 (Reference 2), shows a comparable list of uncertainties and biases that were totaled to obtain the total reactivity effect for the SVEA-96 Optima2 fuel. The ATRIUM 10XM data appears to be missing the bias and uncertainty associated with [( )). Describe whether the value designated as "ATRIUM 10XM Total Uncertainties and Biases" in this table includes the bias and uncertainty associated with (( )), and if not, provide a justification for not including this reactivity effect in Table 2.
In the LAR (Reference 1), Attachment 3, Table 2, lists the uncertainties and biases calculated for the ATRIUM 1OXM, with the intent of demonstrating that the total reactivity effect from all biases and uncertainties for the ATRIUM 1OXM fuel are bounded by the SVEA-96 Optima2 fuel from the previously approved NCS analysis. One of the listed biases is for the "eccentric positioning and fuel assembly channel reactivity effect bias." The NRC staff understands this bias to cover the maximum reactivity increase due to a combination of: (1) eccentric positioning and (2) whether the fuel assembly is channeled or not. Confirm the staff's understanding, or provide clarification as to the intent of this bias.
References:
- 1. "Quad Cities, Units 1 and 2 - Request for License Amendment Regarding Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge." Dated December 14, 2015, ADAMS Accession No. ML15348A396.
- 2. NRC Letter to TVA, Dated December 31, 2014 "Quad Cities Nuclear Power Station, Units 1 and 2- Issuance of Amendments Regarding NETCO Inserts (TAC. NOS.
MF2489 AND MF2490)(RS-13-148), ADAMS Accession No. ML14346A306.
OFFICIAL US& ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION B. Hanson If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1349.
Sincerely, IRA!
Jeanne A Dion, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosures:
- 1. Request for Additional Information, non proprietary
- 2. Request for Additional Information, proprietary cc w/o Enclosure 2:
Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorllpl3-2 Resource RidsNrrLASRohrer Resource RidsRgn3MailCenter Resource RidsAcrs_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrPMQuadCities Resource ADAMS Accession Nos. Proprietary ML16130A572 Non-Proprietary ML16130A570
- via E-mail OFFICE DORULPL3-2/PM DORL/LPL3-2/LA DORL/LPL3-2/B (A)* DORL/LPL3-2/PM NAME JDion SRohrer EMiller JDion DATE 5/11/16 5/9/16 5/12/16 5/12/16 OFFICIAL AGENCY COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION