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| | number = ML17181A197 | | | number = ML17181A197 |
| | issue date = 07/10/2017 | | | issue date = 07/10/2017 |
| | title = Non-Acceptance with Supplemental Information Required Letter to Licensee - I4R-01 Request (CAC MF9758 CAC MF9759) | | | title = Non-Acceptance with Supplemental Information Required Letter to Licensee - I4R-01 Request |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
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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 = CAC:MF9759, CAC:MF9758 | | | project = CAC:MF9758, CAC:MF9759 |
| | stage = Other | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2017 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2017 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:== | | ==SUBJECT:== |
| LASALLE COUNTY STATION, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE: FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PROGRAM RELIEF REQUEST NO. 14R-01 (CAC NOS. MF9758 AND MF9759) | | LASALLE COUNTY STATION, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE: FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PROGRAM RELIEF REQUEST NO. 14R-01 (CAC NOS. MF9758 AND MF9759) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
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| By letter dated May 30, 2017, Exelon Generation Company, LLC (EGC, the licensee) submitted a request for the fourth 10-year inservice inspection (ISi) interval program regarding relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) Code, Section XI, 2007 Edition with the 2008 Addenda. EGC requested the following: | | By letter dated May 30, 2017, Exelon Generation Company, LLC (EGC, the licensee) submitted a request for the fourth 10-year inservice inspection (ISi) interval program regarding relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) Code, Section XI, 2007 Edition with the 2008 Addenda. EGC requested the following: |
| * 14R-01 requests approval of alternative risk-informed ISi program and examination criteria for Examination Category 8-F, 8-J, C-F-1, and C-F-2, pressure retaining piping welds in accordance with ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B, Section XI, Division 1." The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this RR. 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 plant. Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), 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 Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. | | * 14R-01 requests approval of alternative risk-informed ISi program and examination criteria for Examination Category 8-F, 8-J, C-F-1, and C-F-2, pressure retaining piping welds in accordance with ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B, Section XI, Division 1." |
| B. Hanson The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment. ln order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested in the enclosure by July 27, 2017. This will enable the staff to begin its detailed technical review. If the information responsive to the staff's request is not received by the above date, the application will not be accepted for review pursuant to 1 O CFR 2.101, and the NRC will cease its review activities 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 frame in this letter were agreed upon during the telephone discussion with your staff on July 10, 2017. If you have any questions, please contact me at (301) 415-3308. Docket Nos. 50-373 and 50-374 | | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this RR. 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 plant. |
| | Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), 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 Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. |
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| | B. Hanson The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment. |
| | ln order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested in the enclosure by July 27, 2017. This will enable the staff to begin its detailed technical review. If the information responsive to the 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 activities 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 frame in this letter were agreed upon during the telephone discussion with your staff on July 10, 2017. |
| | If you have any questions, please contact me at (301) 415-3308. |
| | Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for supplemental Information cc: Distribution via ListServ Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Background-UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR SUPPLEMENTAL INFORMATION NEEDED REGARDING RELIEF REQUEST NO. 14R-01 FOR LA SALLE COUNTY STATION {LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 {CAC NOS. MF9758 AND MF9759) After reviewing relief request (RR) No. 14R-01, it is not clear if there have been any probabilistic risk assessment (PRA) upgrades, since 2008. The licensee has properly used their latest PRA model but the U.S. Nuclear Regulatory Commission (NRC) staff was not able to verify if the latest model has been peer reviewed based on the information provided in the RR. It appears that no peer review has been conducted since 2008. Additionally, the 2008 peer review used only Revision O of Regulatory Guide (RG) 1.200, rather than the current Revision 2. The RR states that Exelon Generation Company (EGG, the licensee) pertormed a self-assessment against Revision 1 of AG 1.200, but to date there does not appear to be any documentation verifying that a self-assessment against Revision 2 of AG 1.200 has been completed. Supplemental Information Needed from Licensee-The licensee is using a risk-informed approach to support the inservice inspection interval program. Provide the documentation to demonstrate the technical adequacy of their PAA against Revision 2 of AG 1.200 as described below: | | |
| | Request for supplemental Information cc: Distribution via ListServ |
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| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR SUPPLEMENTAL INFORMATION NEEDED REGARDING RELIEF REQUEST NO. 14R-01 FOR LA SALLE COUNTY STATION {LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 |
| | {CAC NOS. MF9758 AND MF9759) |
| | Background-After reviewing relief request (RR) No. 14R-01, it is not clear if there have been any probabilistic risk assessment (PRA) upgrades, since 2008. The licensee has properly used their latest PRA model but the U.S. Nuclear Regulatory Commission (NRC) staff was not able to verify if the latest model has been peer reviewed based on the information provided in the RR. It appears that no peer review has been conducted since 2008. Additionally, the 2008 peer review used only Revision O of Regulatory Guide (RG) 1.200, rather than the current Revision 2. The RR states that Exelon Generation Company (EGG, the licensee) pertormed a self-assessment against Revision 1 of AG 1.200, but to date there does not appear to be any documentation verifying that a self-assessment against Revision 2 of AG 1.200 has been completed. |
| | Supplemental Information Needed from Licensee-The licensee is using a risk-informed approach to support the inservice inspection interval program. Provide the documentation to demonstrate the technical adequacy of their PAA against Revision 2 of AG 1.200 as described below: |
| * In Enclosure LS-LAR-007 to Attachment 1 of the licensee submission (page 11 of 25), it is stated that "the most recent update of the LaSalle PAA model (designated the LS2014A model) was completed in November 2015 as a regularly scheduled update to the previous LS2011A model." | | * In Enclosure LS-LAR-007 to Attachment 1 of the licensee submission (page 11 of 25), it is stated that "the most recent update of the LaSalle PAA model (designated the LS2014A model) was completed in November 2015 as a regularly scheduled update to the previous LS2011A model." |
| * Provide details of all changes to the PRA model since the version reviewed by the 2008 peer review (you may group changes such as "data refinements," but be specific as to other changes, e.g., changes in model structure or methods), justifying whether or not, the change constitutes PAA upgrade as defined in the ASME/ANS [American Society of Mechanical Engineers/American Nuclear Society) PAA standard -"new should be interpreted as new to the subject PRA even though the methodology in question has been applied in other PRAs" [Section 1-A. 1 of ASME/ANS RA-Sa-2009]. | | * Provide details of all changes to the PRA model since the version reviewed by the 2008 peer review (you may group changes such as "data refinements," but be specific as to other changes, e.g., changes in model structure or methods), justifying whether or not, the change constitutes PAA upgrade as defined in the ASME/ANS [American Society of Mechanical Engineers/American Nuclear Society) PAA standard - "new should be interpreted as new to the subject PRA even though the methodology in question has been applied in other PRAs" [Section 1-A. 1 of ASME/ANS RA-Sa-2009]. |
| * If any changes constitute an upgrade, pertorm a focused scope peer review on the affected technical elements (including affected high level requirements as well as all supporting requirements) and provide the results of the review complete with the Facts and Observations/Findings and dispositions addressing any effect upon the application. Enclosure B. Hanson | | * If any changes constitute an upgrade, pertorm a focused scope peer review on the affected technical elements (including affected high level requirements as well as all supporting requirements) and provide the results of the review complete with the Facts and Observations/Findings and dispositions addressing any effect upon the application. |
| | Enclosure |
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| | B. Hanson |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LASALLE COUNTY STATION, UNITS 1AND2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE FOURTH 10-YEAR NO. 14R-01 (CAC NOS. MF9758 AND MF9759) DATED JULY 10, 2017 DISTRIBUTION: PUBLIC LPL3 R/F RidsNrrPMLaSalle Resource RidsRgn3MailCenter Resource RidsOgcRp Resource RidsNrrOorllp13 Resource ADAMS A ccess1on: ML17181A197 OFFICE NRR/DORL/LPL3/PM NAME BVaidya DATE 07/10/17 OFFICE NRR/DORL/LPL3/BC NAME DWrona DATE 07/10/17 RidsNrrDraApla Resource RidsNrrlASRohrer Resource RidsAcrs_MailCTR Resource LFields, NRR/DRNAPLA RGalucci, NRR/DRNAPLA *N btt'lh o su s an 1a c anoe 1n th eema1 I NRR/DORL/LPL3/LA NRR/DRNAPLNBC SRohrer SRosenberg* 07/05/17 06/27/17 NRR/DORL/LPL3/PM BVaidya 07/10/17 OFFICIAL RECORD COPY | | LASALLE COUNTY STATION, UNITS 1AND2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE FOURTH 10-YEAR NO. 14R-01 (CAC NOS. MF9758 AND MF9759) DATED JULY 10, 2017 DISTRIBUTION: |
| }} | | PUBLIC RidsNrrDraApla Resource LPL3 R/F RidsNrrlASRohrer Resource RidsNrrPMLaSalle Resource RidsAcrs_MailCTR Resource RidsRgn3MailCenter Resource LFields, NRR/DRNAPLA RidsOgcRp Resource RGalucci, NRR/DRNAPLA RidsNrrOorllp13 Resource ADAMS A ccess1on: ML17181A197 *N o su b stant '1al h c anoe 1n th eema1 I OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRNAPLNBC NAME BVaidya SRohrer SRosenberg* |
| | DATE 07/10/17 07/05/17 06/27/17 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME DWrona BVaidya DATE 07/10/17 07/10/17 OFFICIAL RECORD COPY}} |
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Category:Letter
MONTHYEARRS-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 05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024 Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000373/20244012024-09-27027 September 2024 County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401 ML24263A2062024-09-19019 September 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS ML24260A0492024-09-16016 September 2024 Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 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 05000373/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005) IR 05000373/20244022024-08-28028 August 2024 County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer IR 05000373/20240022024-08-13013 August 2024 County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002 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 05000373/20244202024-08-0505 August 2024 County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420 05000373/LER-2024-003-01, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024 Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions ML24178A2522024-06-27027 June 2024 County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation 05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-19019 June 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer 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 05000373/LER-2024-003, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-06-0606 June 2024 Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded IR 05000373/20240102024-05-29029 May 2024 County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010 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 05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-17017 May 2024 Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip ML24131A1512024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 IR 05000373/20240012024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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 05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded2024-04-26026 April 2024 Core Operating Limits Report Thermal Limits Exceeded ML24108A1562024-04-15015 April 2024 Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11 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 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 ML24071A2122024-03-12012 March 2024 County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection IR 05000373/20230062024-02-28028 February 2024 Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006) RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 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 ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 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 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23153A1562023-06-0202 June 2023 NRR E-mail Capture - RAI LaSalle pressure-temperature Limits Report (PTLR) Amendment Request ML23150A2482023-05-25025 May 2023 NRR E-mail Capture - RAI Re LaSalle Downcomer Analysis Amendment Request ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22361A0792022-12-27027 December 2022 Notification of NRC Baseline Inspection and Request for Information (05000374/2023001) 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 ML22138A4112022-05-18018 May 2022 NRR E-mail Capture - Lasalle 1 and 2 - (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Changes to TS Sections 4.3.1 and 5.6.5 (EPID-L-2021-LLA-0124) ML22126A0392022-05-0606 May 2022 NRR E-mail Capture - Lasalle 1 and 2 Draft (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to TS Sections 4.3.1 and 5.6.5 ML22097A0832022-04-0707 April 2022 County Station Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000373/2022403 and 05000374/2022403 ML22062B0232022-03-0303 March 2022 NRR E-mail Capture - EPID-L-2022-LLR-0028, LaSalle Unit 1, Request for Additional Information (Rai), LaSalle Unit 1, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs 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 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 ML21292A1782021-10-19019 October 2021 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000373/2022010 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21207A0072021-07-26026 July 2021 NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) License Amendment Request to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology(EPID-L-2021-LLA-0016) ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21187A2972021-07-0707 July 2021 Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection 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 ML21119A2282021-04-29029 April 2021 NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle, EPID-L-2020-LLA-0018, License Amendment Request (LAR) TSTF-505 ML21077A1902021-03-18018 March 2021 NRR E-mail Capture - Lasalle Units 1 and 2 - Request for Additional Information (RAI) Request for License Amendment Regarding Ultimate Heat Sink, (EPID-L-2020-LLA-0165) ML21068A2762021-03-0909 March 2021 NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair (EPID-L-2020-LLA-0016) ML21067A6752021-03-0808 March 2021 NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) UHS Amendment Request (EPID-L-2020-LLA-0165) ML21060B4352021-03-0101 March 2021 NRR E-mail Capture - Second Round - Request for Additional Information (Rais) EPID-L-2020-LLA-0018, LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2 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 ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing 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) ML21048A0432021-02-16016 February 2021 County Station - Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information - Inspection Report 05000373/2021011 and 05000374/2021011 ML20364A2452020-12-29029 December 2020 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000373/2021002; 05000374/2021002 ML20346A1042020-12-11011 December 2020 NRR E-mail Capture - LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69 ML20330A1892020-11-25025 November 2020 Request for Information for an NRC Post-Approval Site Inspection for License Renewal; Inspection Report 05000374/2021010 ML20321A0852020-11-16016 November 2020 Notification of NRC Baseline Inspection and Request for Information (05000374/2021001) ML20247J4082020-09-29029 September 2020 Apla Request for Additional Information LAR 50.69 and TSTF-505 (Epids L-2020-LLA-0017) and ML20253A3422020-09-17017 September 2020 Correction to Request for Additional Information Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (EPID-2020-LLA-0017) ML20253A2272020-09-16016 September 2020 Correction to Request for Additional Information Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20240A2182020-09-0303 September 2020 Request for Additional Information Regarding Amendment Request for Amendments to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Co ML20239A7262020-08-27027 August 2020 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19120A2302019-04-29029 April 2019 Ltr. 04/29/19 LaSalle County Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000373/2019012; 05000374/2019012 (DRS-M.Jones) ML19087A2682019-03-28028 March 2019 NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle 1 and 2, EPID-L-2018-LLA-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG ML19065A0902019-03-0505 March 2019 NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Additional Draft Request for Additional Information (RAI) ML19058A2392019-02-27027 February 2019 Information Request to Support Upcoming Problem Identification and Resolution Inspection at LaSalle County Station, Units 1 and 2 ML19036A6562019-02-0505 February 2019 NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0123, Relief Request I3R-15, Third Inservice Inspection Interval, Request for Additional Information (RAI) ML19050A0042019-01-22022 January 2019 NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Draft Request for Additional Information (RAI) 2024-07-12
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2017 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:
LASALLE COUNTY STATION, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE: FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PROGRAM RELIEF REQUEST NO. 14R-01 (CAC NOS. MF9758 AND MF9759)
Dear Mr. Hanson:
By letter dated May 30, 2017, Exelon Generation Company, LLC (EGC, the licensee) submitted a request for the fourth 10-year inservice inspection (ISi) interval program regarding relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) Code,Section XI, 2007 Edition with the 2008 Addenda. EGC requested the following:
- 14R-01 requests approval of alternative risk-informed ISi program and examination criteria for Examination Category 8-F, 8-J, C-F-1, and C-F-2, pressure retaining piping welds in accordance with ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B,Section XI, Division 1."
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this RR. 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 plant.
Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), 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 Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
B. Hanson The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
ln order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested in the enclosure by July 27, 2017. This will enable the staff to begin its detailed technical review. If the information responsive to the 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 activities 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 frame in this letter were agreed upon during the telephone discussion with your staff on July 10, 2017.
If you have any questions, please contact me at (301) 415-3308.
Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Request for supplemental Information cc: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR SUPPLEMENTAL INFORMATION NEEDED REGARDING RELIEF REQUEST NO. 14R-01 FOR LA SALLE COUNTY STATION {LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
{CAC NOS. MF9758 AND MF9759)
Background-After reviewing relief request (RR) No. 14R-01, it is not clear if there have been any probabilistic risk assessment (PRA) upgrades, since 2008. The licensee has properly used their latest PRA model but the U.S. Nuclear Regulatory Commission (NRC) staff was not able to verify if the latest model has been peer reviewed based on the information provided in the RR. It appears that no peer review has been conducted since 2008. Additionally, the 2008 peer review used only Revision O of Regulatory Guide (RG) 1.200, rather than the current Revision 2. The RR states that Exelon Generation Company (EGG, the licensee) pertormed a self-assessment against Revision 1 of AG 1.200, but to date there does not appear to be any documentation verifying that a self-assessment against Revision 2 of AG 1.200 has been completed.
Supplemental Information Needed from Licensee-The licensee is using a risk-informed approach to support the inservice inspection interval program. Provide the documentation to demonstrate the technical adequacy of their PAA against Revision 2 of AG 1.200 as described below:
- In Enclosure LS-LAR-007 to Attachment 1 of the licensee submission (page 11 of 25), it is stated that "the most recent update of the LaSalle PAA model (designated the LS2014A model) was completed in November 2015 as a regularly scheduled update to the previous LS2011A model."
- Provide details of all changes to the PRA model since the version reviewed by the 2008 peer review (you may group changes such as "data refinements," but be specific as to other changes, e.g., changes in model structure or methods), justifying whether or not, the change constitutes PAA upgrade as defined in the ASME/ANS [American Society of Mechanical Engineers/American Nuclear Society) PAA standard - "new should be interpreted as new to the subject PRA even though the methodology in question has been applied in other PRAs" [Section 1-A. 1 of ASME/ANS RA-Sa-2009].
- If any changes constitute an upgrade, pertorm a focused scope peer review on the affected technical elements (including affected high level requirements as well as all supporting requirements) and provide the results of the review complete with the Facts and Observations/Findings and dispositions addressing any effect upon the application.
Enclosure
B. Hanson
SUBJECT:
LASALLE COUNTY STATION, UNITS 1AND2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE FOURTH 10-YEAR NO. 14R-01 (CAC NOS. MF9758 AND MF9759) DATED JULY 10, 2017 DISTRIBUTION:
PUBLIC RidsNrrDraApla Resource LPL3 R/F RidsNrrlASRohrer Resource RidsNrrPMLaSalle Resource RidsAcrs_MailCTR Resource RidsRgn3MailCenter Resource LFields, NRR/DRNAPLA RidsOgcRp Resource RGalucci, NRR/DRNAPLA RidsNrrOorllp13 Resource ADAMS A ccess1on: ML17181A197 *N o su b stant '1al h c anoe 1n th eema1 I OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRNAPLNBC NAME BVaidya SRohrer SRosenberg*
DATE 07/10/17 07/05/17 06/27/17 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME DWrona BVaidya DATE 07/10/17 07/10/17 OFFICIAL RECORD COPY