|
|
(2 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML113470622 | | | number = ML113470622 |
| | issue date = 12/19/2011 | | | issue date = 12/19/2011 |
| | title = Quad Cities, Units 1 and 2 - Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration | | | title = Request for Additional Information Related to Technical Specification Change for Safety Limit Minimum Critical Power Ration |
| | author name = Wiebe J S | | | author name = Wiebe J |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000254, 05000265 | | | docket = 05000254, 05000265 |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
| | |
| | ==SUBJECT:== |
| | QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613) |
|
| |
|
| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. | | |
| By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information. | | By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information. |
| The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter. 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 NRC's goal of efficient and effective use of staff resources. | | The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter. |
| M. Pacilio If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. | | 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 NRC's goal of efficient and effective use of staff resources. |
| Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 Request for Additional cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND DOCKET NOS. 50-254 AND In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML 111590206, ML 112650386, ML 113070426, and ML 113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A. | | |
| Provide a complete listing of computer codes used in the implementation of 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications. During the conference call on November 18, 2011, your staff stated that you were evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative. | | M. Pacilio -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. |
| Describe how you are establishing this threshold. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation. | | Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111590206, ML112650386, ML113070426, and ML113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: |
| | : 1. CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A. |
| | Provide a complete listing of computer codes used in the implementation of CENPD 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications. |
| | : 2. During the conference call on November 18, 2011, your staff stated that you were re evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative. Describe how you are establishing this threshold. |
| | : 3. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation. |
| Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal. | | Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal. |
| M. Pacilio -If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. | | |
| Docket Nos. 50-254 and 50-265 Request for Additional cc w/encl: Distribution via LPL3-2 RidsNrrDorlLpl3-2 RidsNrrLASRohrer RidsAcrsAcnw_MailCTR RidsNrrPMQuadCities Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDssSrxb Resource ADAMS Accession No. ML 113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC NAME JWiebe SRohrer TUlses JZimmerman DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy}}
| | M. Pacilio - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606. |
| | Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsOgcRp Resource LPL3-2 RlF RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsNrrLASRohrer Resource RidsNrrDssSrxb Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMQuadCities Resource ADAMS Accession No. ML113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC SRohrer TUlses JZimmerman NAME JWiebe DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy}} |
|
---|
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0482024-07-12012 July 2024 Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24135A0182024-05-13013 May 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment ML24102A2422024-04-10010 April 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments ML24066A1532024-03-0606 March 2024 NRR E-mail Capture - Request for Additional Information TSTF-505, R2, Provide Risk-Informed Extended Completion Times, RITSTF (Risk-Informed Technical Specification Task Force) Initiative 4b and 10 CFR 50.69 License Amendments ML24053A1192024-02-22022 February 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000265/2024010 and 05000254/2024010 ML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 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 ML22164A8582022-06-13013 June 2022 NRR E-mail Capture - RAI Alternative RV-09, MSSVs ML22164A8562022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves 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) 2024-07-12
[Table view] Category:Letter
MONTHYEARIR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024 Correction to Registration of Use of Casks to Store Spent Fuel ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24247A1642024-09-30030 September 2024 Alternative Request RP-01 IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel SVP-24-046, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24141A2102024-05-20020 May 2024 Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 SVP-24-031, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-10010 May 2024 Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report ML24109A0662024-05-0202 May 2024 – Relief Request I5R-26, Revision 0 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 ML24114A1712024-04-23023 April 2024 State of Illinois (IEMA-OHS) Comment Quad Cities HI-STORM Exemption Environmental Assessment SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report SVP-24-023, Ile Outline Submittal Letter2024-03-29029 March 2024 Ile Outline Submittal Letter RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter RS-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval IR 05000254/20230062024-02-28028 February 2024 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2023006 and 05000265/2023006) 2024-09-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION CHANGE FOR SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NOS. ME6383 AND ME7613)
Dear Mr. Pacilio:
By letters to the Nuclear Regulatory Commission (NRC) dated June 7,2011, and November 22, 2011, Exelon Generation Company, LLC (Exelon) submitted requests to revise the technical specification safety limit minimum critical power ratio, for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively. By letters dated September 21, 2011, and November 2, 2011, Exelon submitted additional information in response to our requests for additional information.
The NRC staff is reviewing your submittal and based on your submittals and audits of Westinghouse documents on October 19, 2011, and November 10, 2011, has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This information was provided to your staff during a discussion on November 14, 2011. During a discussion with your staff on December 8, 2011, it was agreed that you would provide a response 30 days from the date of this letter.
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 NRC's goal of efficient and effective use of staff resources.
M. Pacilio -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.
Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 In reviewing the Exelon Generation Company's (Exelon's) submittals dated June 7, September 21, November 2, and November 22, 2011 (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111590206, ML112650386, ML113070426, and ML113260348, respectively), and audits of Westinghouse documents on October 19, and November 10, 2011, related to the revision of the technical specification safety limit minimum critical power ratio (SLMCPR), for the Quad Cities Nuclear Power Station, Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review:
- 1. CENPD-300-P-A, Section 1.3 states, "Appendix A to this report provides a brief description of the computer codes used in ABB reload analysis methodology." The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staffs acceptance applies only to the matters described in the report. In Exelon's submittal dated June 7,2011, and supplement dated November 2,2011, you identified several computer codes that are not listed in Appendix A and therefore not considered in the staff's acceptance of CENPD-300-P-A.
Provide a complete listing of computer codes used in the implementation of CENPD 300-P-A for determining the SLMCPR. Justify your use of these codes for the NRC approved analytical method (i.e., CENPD-300-P-A) listed in the Technical Specifications.
- 2. During the conference call on November 18, 2011, your staff stated that you were re evaluating the MWd/MT threshold below which the Unit 1 SLMCPR was assured to be conservative. Describe how you are establishing this threshold.
- 3. The CENPD-300-P-A acceptance letter dated May 24, 1996, states that the staff finds the report and related documents to be acceptable to the extent specified and under the limitations delineated in the NRC evaluation.
Confirm that your implementation of CENPD-300-P-A for your June 6 and November 22, 2011, submittals continue to meet these conditions and limitations as described in your June 15, 2005 (ADAMS Accession No. ML060620352) submittal.
M. Pacilio - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-6606.
Sincerely, IRA by Araceli T.Billoch Colon forI Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp Resource LPL3-2 RlF RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsNrrLASRohrer Resource RidsNrrDssSrxb Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMQuadCities Resource ADAMS Accession No. ML113470622 NRR-088 OFFICE LPL3-21PM LPL3-2/LA SRXB/BC LPL3-2/BC SRohrer TUlses JZimmerman NAME JWiebe DATE 12/15/11 12/14/11 12/19/11 12/19/11 OFFICIAL RECORD COpy