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| | number = ML12331A277 | | | number = ML12331A277 |
| | issue date = 11/28/2012 | | | issue date = 11/28/2012 |
| | title = Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 & Supplemental Information Needed for Acceptance of RLA, I5R-02 | | | title = Supplemental Information Needed for Acceptance of RLA, I5R-02 |
| | author name = Mozafari B L | | | author name = Mozafari B |
| | 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 = 05000454, 05000455, 05000456, 05000457 | | | docket = 05000454, 05000455, 05000456, 05000457 |
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| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = TAC:ME9670, TAC:ME9671, TAC:ME9685, TAC:ME9684 | | | project = TAC:ME9670, TAC:ME9671, TAC:ME9684, TAC:ME9685 |
| | stage = Acceptance Review | | | stage = Acceptance Review |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 28, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 28, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: FIFTH INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND RELIEF REQUESTS, 15R-02, REQUEST FOR ALTERNATE INFORMED SELECTION AND EXAMINATION CRITERIA FOR EXAMINATION CATEGORIES B-F. B-J, C-F-1, AND C-F-2 PRESSURE PIPING WELDS (TAC NOS. ME9684, ME9685, ME9670, AND ME9671) | | DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: FIFTH INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND RELIEF REQUESTS, 15R-02, REQUEST FOR ALTERNATE RISK INFORMED SELECTION AND EXAMINATION CRITERIA FOR EXAMINATION CATEGORIES B-F. B-J, C-F-1, AND C-F-2 PRESSURE PIPING WELDS (TAC NOS. ME9684, ME9685, ME9670, AND ME9671) |
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| ==Dear Pacilio:== | | ==Dear Pacilio:== |
| By two letters dated September 28,2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 12275A069 and ML 12275A070), Exelon Generation Company, LLC (Exelon, the licensee) submitted their fifth interval inservice inspection (lSI) program and relief requests (RRs) for Dresden Nuclear Power Station, Unit Nos. 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Dresden and Quad Cities). The proposed RRs would allow Dresden and Quad Cities to use the Electric Power Research Institute Tropical Report 112657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," dated December 1999, as an alternative to the American Society of Mechanical Engineers, Section XI, Code examination requirements for lSI of Class 1 and 2 piping welds (Categories B-F, B-J, C-F-1, and C-F-2) along with two enhancements to provide acceptable level of quality and safety required by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(i). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of the RRs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plants. Pursuant to 10 CFR 50.55a(a)(3)(i), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of 10 CFR 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent M. Pacilio -assessment regarding the acceptability of the RRs in terms of regulatory requirements and the protection of public health and safety and the environment. In order to make the application complete, the NRC staff requests that Exelon supplement the application to address the information requested in the enclosure by November 29, 2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review actives associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and associated time frames in this letter were discussed with your staff on November 15, 2012. If you have any questions, please contact Carolyn Faria at (301) 415-4050. Sincerely, Brenda Mozafari, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254, 50-265, 50-237 and 50-249 Supplemental Information cc w/encl: Distribution via SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-237, 50-249, 50-254 and 50-265 8y letters dated September 28,2012, Exelon Generation Company, LLC (Exelon, the licensee) submitted their fifth interval inservice inspection (lSI) program and relief requests (RRs) for Dresden Nuclear Power Station, Unit Nos. 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Dresden and Quad Cities). The proposed RRs would allow Dresden and Quad Cities to use Electric Power Research Institute (EPRI) Tropical Report (TA) 12657, Revision A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," dated December 1999, as an alternative to the American Society of Mechanical Engineers (ASME) Section XI, Code examination requirements for lSI Class 1 and 2 piping welds (Categories 8-F, 8-J, C-F-1, and C-F-2), along with two enhancements: (1) the requirements of paragraph-2430, "Additional Examinations" contained in Code Case N-578-1 in lieu of the evaluation and sample expansion requirements in Section 3.6.6.2, "RI-ISI Selected Examinations" of EPRI TR-112657, and (2) provisions listed in Table 1, Examination Category R-A, "Risk-Informed Piping Examinations", to provide acceptable level of quality and safety required by Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(i). To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following supplemental information. Exelon indicates that the risk impact assessment was completed as part of the original baseline RI-ISI program. The submittal further states that the change in risk was assessed, for the fifth interval, using the initial 1989 Edition, No Addenda ASME Section XI program. The acceptance criteria is described in Regulatory Guides 1.174 and 1.178. Please provide the risk results from the assessment that was made by comparing the proposed lSI program to the initial Section XI requirements that justify that the acceptance criteria is met for the fifth interval. Enclosure M. Pacilio -2 assessment regarding the acceptability of the RRs in terms of regulatory requirements and the protection of public health and safety and the environment. In order to make the application complete, the NRC staff requests that Exelon supplement the application to address the information requested in the enclosure by November 29, 2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review actives associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and associated time frames in this letter were discussed with your staff on November 15, 2012. If you have any questions, please contact Carolyn Faria at (301) 415-4050. Sincerely, / RA Nicholas DiFrancesco for / Brenda Mozafari, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-456, 50-457, 50-454 and 50-455 Supplemental Information cc w/encl: Distribution via RidsNrrDorl Resource Branch Reading File RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDraApla Resource RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsNrrLASRohrer Resource ADAMS Accession No. ML12331A277 *via e-mail OFFICE NRRlDORLlLPL3-2/PE NRR/DORLlLPL3-2/LA NRR/DRAlAPLAlBC* NAME CFaria SRohrer DHarrison DATE | | |
| * 11/26/12 11/27/12 i 11/27/12 i OFFICE | | By two letters dated September 28,2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12275A069 and ML12275A070), Exelon Generation Company, LLC (Exelon, the licensee) submitted their fifth interval inservice inspection (lSI) program and relief requests (RRs) for Dresden Nuclear Power Station, Unit Nos. 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Dresden and Quad Cities). The proposed RRs would allow Dresden and Quad Cities to use the Electric Power Research Institute Tropical Report 112657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," dated December 1999, as an alternative to the American Society of Mechanical Engineers, Section XI, Code examination requirements for lSI of Class 1 and 2 piping welds (Categories B-F, B-J, C-F-1, and C-F-2) along with two enhancements to provide acceptable level of quality and safety required by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(i). |
| * NRRlDORULPL3-2/BC NRR/DORLlLPL3-2/PM INAME 1 MDudek BMozafari (NDifrancesco for) DATE 111/28/12 11/28/12 OFFICIAL RECORD | | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of the RRs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plants. |
| }} | | Pursuant to 10 CFR 50.55a(a)(3)(i), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of 10 CFR 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. |
| | The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent |
| | |
| | M. Pacilio - 2 assessment regarding the acceptability of the RRs in terms of regulatory requirements and the protection of public health and safety and the environment. |
| | In order to make the application complete, the NRC staff requests that Exelon supplement the application to address the information requested in the enclosure by November 29, 2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review actives associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. |
| | The information requested and associated time frames in this letter were discussed with your staff on November 15, 2012. |
| | If you have any questions, please contact Carolyn Faria at (301) 415-4050. |
| | Sincerely, Brenda Mozafari, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254, 50-265, 50-237 and 50-249 |
| | |
| | ==Enclosure:== |
| | |
| | Supplemental Information Request cc w/encl: Distribution via Listserv |
| | |
| | SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-237, 50-249, 50-254 and 50-265 8y letters dated September 28,2012, Exelon Generation Company, LLC (Exelon, the licensee) submitted their fifth interval inservice inspection (lSI) program and relief requests (RRs) for Dresden Nuclear Power Station, Unit Nos. 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Dresden and Quad Cities). The proposed RRs would allow Dresden and Quad Cities to use Electric Power Research Institute (EPRI) Tropical Report (TA) 12657, Revision 8 A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," dated December 1999, as an alternative to the American Society of Mechanical Engineers (ASME) Section XI, Code examination requirements for lSI Class 1 and 2 piping welds (Categories 8-F, 8-J, C-F-1, and C-F-2), along with two enhancements: (1) the requirements of paragraph-2430, "Additional Examinations" contained in Code Case N-578-1 in lieu of the evaluation and sample expansion requirements in Section 3.6.6.2, "RI-ISI Selected Examinations" of EPRI TR-112657, and (2) provisions listed in Table 1, Examination Category R-A, "Risk-Informed Piping Examinations", to provide acceptable level of quality and safety required by Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(i). To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following supplemental information. |
| | : 1. Exelon indicates that the risk impact assessment was completed as part of the original baseline RI-ISI program. The submittal further states that the change in risk was re assessed, for the fifth interval, using the initial 1989 Edition, No Addenda ASME Section XI program. The acceptance criteria is described in Regulatory Guides 1.174 and 1.178. |
| | Please provide the risk results from the assessment that was made by comparing the proposed lSI program to the initial Section XI requirements that justify that the acceptance criteria is met for the fifth interval. |
| | Enclosure |
| | |
| | ML12331A277 *via e-mail OFFICE NRRlDORLlLPL3-2/PE NRR/DORLlLPL3-2/LA NRR/DRAlAPLAlBC* |
| | NAME CFaria SRohrer DHarrison DATE |
| | * 11/26/12 11/27/12 i 11/27/12 i OFFICE |
| | * NRRlDORULPL3-2/BC NRR/DORLlLPL3-2/PM NAME 1 MDudek BMozafari (NDifrancesco for) I DATE 111/28/12 11/28/12}} |
Letter Sequence Acceptance Review |
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MONTHYEARML1100404192011-02-15015 February 2011 Summary of Telephone Conference Call Held on December 6, 2010, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operating, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application (Tac No. MC9669) Project stage: Other ML1108206892011-04-19019 April 2011 February 24, 2011, Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application Project stage: Other RS-12-151, Fifth Interval Lnservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Lnservice Inspection Program Plan and Relief Requests Project stage: Request RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Inservice Inspection Program Plan and Relief Requests Project stage: Request RS-12-202, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-19019 November 2012 Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01 Project stage: Supplement ML12331A2772012-11-28028 November 2012 Supplemental Information Needed for Acceptance of RLA, I5R-02 Project stage: Acceptance Review RS-12-205, Supplement to Fifth Inservice Inspection Interval Relief Request I5R-022012-11-28028 November 2012 Supplement to Fifth Inservice Inspection Interval Relief Request I5R-02 Project stage: Supplement RS-12-203, Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-28028 November 2012 Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01 Project stage: Supplement ML12348A8302012-12-13013 December 2012 NRR E-mail Capture - Acceptance Review of Dresden, Units 2 and 3, Relief Request I5R-02 Project stage: Acceptance Review ML12348A8312012-12-13013 December 2012 NRR E-mail Capture - Acceptance Review of Quad Cities, Units 1 and 2, Relief Request I5R-02 Project stage: Acceptance Review ML12348A4272012-12-21021 December 2012 Request for Additional Information Related to the Request for Alternative I5R-03 Project stage: RAI RS-13-005, Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-032013-01-10010 January 2013 Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-03 Project stage: Supplement RS-13-040, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-042013-01-24024 January 2013 Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04 Project stage: Supplement ML13099A2802013-04-0909 April 2013 NRR E-mail Capture - Finalized Dresden RAI I5R-01 I5R-02 and I5R-07 Project stage: RAI ML13110A0072013-04-19019 April 2013 NRR E-mail Capture - RAI for Dresden Units 2 and 3 Exelon Generation Company, LLC Relief Request Nos. I5R-01, I5R-02, and I5R-07 Docket Numbers 50-237 and 50-249 TAC Nos. ME9682-83, ME9684-85, and ME9692-93 Project stage: RAI ML13115A2322013-04-24024 April 2013 NRR E-mail Capture - Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information Project stage: RAI ML13123A0852013-05-0202 May 2013 NRR E-mail Capture - Dresden Relief Request No. I5R-02 - Request for Additional Information Project stage: RAI ML13123A0862013-05-0202 May 2013 NRR E-mail Capture - Quad Cities Relief Request No. I5R-02 - Request for Additional Information Project stage: RAI RS-13-147, Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-062013-05-30030 May 2013 Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-06 Project stage: Request RS-13-107, Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-072013-06-0303 June 2013 Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-07 Project stage: Supplement ML13267A0972013-09-30030 September 2013 Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Inspection Program Project stage: Approval ML13258A0032013-09-30030 September 2013 Safety Evaluation for the Fifth 10-Year Interval Inservice Inspection Relief Request for Exelon Generation Boiling Water Reactor (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc.) Project stage: Approval ML13260A5852013-09-30030 September 2013 Cover Letter -Safety Evaluation in Support of Request for Relief Associated with the Fifth 10-Year Interval Inservice Inspection Program (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc Project stage: Approval 2013-01-10
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Category:Letter
MONTHYEARML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024 Cycle 27 Core Operating Limits Report RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024 Relief Requests Associated with the Fifth Inservice Inspection Interval IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024 Both Trains of Control Room Ventilation Temperature Control System Inoperable ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) IR 05000454/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000454/20240112024-08-0808 August 2024 Phase 2 Post- Approval License Renewal Report 05000454/2024011 IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter IR 05000454/20240022024-07-26026 July 2024 Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter ML24170A7652024-06-19019 June 2024 Confirmation of Initial License Examination 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 ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 IR 05000454/20240012024-05-10010 May 2024 Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001 BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 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 IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 ML24116A1192024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary ML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information ML24053A3382024-02-22022 February 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML24039A0412024-01-30030 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Braidwood Request for Alternative (I4R-18) ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML23018A1632023-01-18018 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22241A0522022-08-29029 August 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004 ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) 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 ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21228A2352021-08-17017 August 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004 ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 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 ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 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) ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information ML20294A5492020-10-21021 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20104C1452020-04-10010 April 2020 NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request 2024-09-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 28, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: FIFTH INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND RELIEF REQUESTS, 15R-02, REQUEST FOR ALTERNATE RISK INFORMED SELECTION AND EXAMINATION CRITERIA FOR EXAMINATION CATEGORIES B-F. B-J, C-F-1, AND C-F-2 PRESSURE PIPING WELDS (TAC NOS. ME9684, ME9685, ME9670, AND ME9671)
Dear Pacilio:
By two letters dated September 28,2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12275A069 and ML12275A070), Exelon Generation Company, LLC (Exelon, the licensee) submitted their fifth interval inservice inspection (lSI) program and relief requests (RRs) for Dresden Nuclear Power Station, Unit Nos. 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Dresden and Quad Cities). The proposed RRs would allow Dresden and Quad Cities to use the Electric Power Research Institute Tropical Report 112657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," dated December 1999, as an alternative to the American Society of Mechanical Engineers,Section XI, Code examination requirements for lSI of Class 1 and 2 piping welds (Categories B-F, B-J, C-F-1, and C-F-2) along with two enhancements to provide acceptable level of quality and safety required by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(i).
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of the RRs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plants.
Pursuant to 10 CFR 50.55a(a)(3)(i), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of 10 CFR 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent
M. Pacilio - 2 assessment regarding the acceptability of the RRs in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that Exelon supplement the application to address the information requested in the enclosure by November 29, 2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review actives associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frames in this letter were discussed with your staff on November 15, 2012.
If you have any questions, please contact Carolyn Faria at (301) 415-4050.
Sincerely, Brenda Mozafari, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254, 50-265, 50-237 and 50-249
Enclosure:
Supplemental Information Request cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-237, 50-249, 50-254 and 50-265 8y letters dated September 28,2012, Exelon Generation Company, LLC (Exelon, the licensee) submitted their fifth interval inservice inspection (lSI) program and relief requests (RRs) for Dresden Nuclear Power Station, Unit Nos. 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Dresden and Quad Cities). The proposed RRs would allow Dresden and Quad Cities to use Electric Power Research Institute (EPRI) Tropical Report (TA) 12657, Revision 8 A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," dated December 1999, as an alternative to the American Society of Mechanical Engineers (ASME)Section XI, Code examination requirements for lSI Class 1 and 2 piping welds (Categories 8-F, 8-J, C-F-1, and C-F-2), along with two enhancements: (1) the requirements of paragraph-2430, "Additional Examinations" contained in Code Case N-578-1 in lieu of the evaluation and sample expansion requirements in Section 3.6.6.2, "RI-ISI Selected Examinations" of EPRI TR-112657, and (2) provisions listed in Table 1, Examination Category R-A, "Risk-Informed Piping Examinations", to provide acceptable level of quality and safety required by Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(i). To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following supplemental information.
- 1. Exelon indicates that the risk impact assessment was completed as part of the original baseline RI-ISI program. The submittal further states that the change in risk was re assessed, for the fifth interval, using the initial 1989 Edition, No Addenda ASME Section XI program. The acceptance criteria is described in Regulatory Guides 1.174 and 1.178.
Please provide the risk results from the assessment that was made by comparing the proposed lSI program to the initial Section XI requirements that justify that the acceptance criteria is met for the fifth interval.
Enclosure
ML12331A277 *via e-mail OFFICE NRRlDORLlLPL3-2/PE NRR/DORLlLPL3-2/LA NRR/DRAlAPLAlBC*
NAME CFaria SRohrer DHarrison DATE
- 11/26/12 11/27/12 i 11/27/12 i OFFICE
- NRRlDORULPL3-2/BC NRR/DORLlLPL3-2/PM NAME 1 MDudek BMozafari (NDifrancesco for) I DATE 111/28/12 11/28/12