Letter Sequence Supplement |
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TAC:MF5346, Control Room Habitability (Approved, Closed) TAC:MF5347, Control Room Habitability (Approved, Closed) |
Results
Other: ML15104A782, ML15196A045, ML15196A115, ML16202A033, RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application, RS-15-194, Responds to NRC Requests for Additional Information, Set 6, Dated July 7, 2015 Related to the License Renewal Application, RS-15-305, Corrections to the License Renewal Application Dated December 9, 2014, RS-15-306, Submittal of 10 CFR 54.21(b) Annual Amendment to the License Renewal Application, RS-16-033, Update to Commitment 47 Related to the License Renewal Application, RS-16-068, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application, RS-16-128, Second 10 CFR 54.21(b) Annual Amendment to the License Renewal Application
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MONTHYEARML15104A7822015-05-0808 May 2015 Scoping and Screening Methodology Audit Report Regarding LaSalle County Station, Units 1 and 2 Project stage: Other ML15111A1372015-05-14014 May 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 1 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15125A1982015-05-29029 May 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 2 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15131A4132015-06-0808 June 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 3 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15140A1922015-06-0808 June 2015 Summary of Telephone Conference Call Held on May 13, 2015, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Co., LLC, Concerning Requests for Additional Information, Set 2 Pertaining to the Lasalle County Station License Project stage: RAI ML15146A2622015-06-19019 June 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application-Set 4 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-165, Response to NRC Requests for Additional Information, Set 2, Dated May 29, 2015 Related to the License Renewal Application2015-06-25025 June 2015 Response to NRC Requests for Additional Information, Set 2, Dated May 29, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-171, Response to NRC Requests for Additional Information, Set 3, Dated June 8, 2015, Related to the License Renewal Application2015-07-0101 July 2015 Response to NRC Requests for Additional Information, Set 3, Dated June 8, 2015, Related to the License Renewal Application Project stage: Response to RAI ML15159A9002015-07-0606 July 2015 Telephone Conference Call Held on May 20, 2015, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Co., LLC, Requests for Additional Information, Set 3 Pertaining to the LaSalle County Station License Renewal Application ( Project stage: RAI ML15163A0712015-07-0707 July 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 6 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15159A2082015-07-0707 July 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 5 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-180, Response to NRC Requests for Additional Information, Set 4, Dated June 19, 2015 Related to the License Renewal Application2015-07-15015 July 2015 Response to NRC Requests for Additional Information, Set 4, Dated June 19, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-198, Request for Schedule Change Related to Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Review of License Renewal Application (TAC Nos. MF5347 and MF5346)2015-07-16016 July 2015 Request for Schedule Change Related to Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Review of License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: Request ML15196A5292015-07-27027 July 2015 Requests for Additional Information for the Review of the Lasalle County Station, Units 1 and 2 License Renewal Application - Set 7 (Tac Nos. MF5347 and MF5346) Project stage: RAI RS-15-194, Responds to NRC Requests for Additional Information, Set 6, Dated July 7, 2015 Related to the License Renewal Application2015-08-0606 August 2015 Responds to NRC Requests for Additional Information, Set 6, Dated July 7, 2015 Related to the License Renewal Application Project stage: Other RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application2015-08-0606 August 2015 Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application Project stage: Other ML15204A6302015-08-18018 August 2015 Requests for Additional Information for the Review of the LaSalle County Station Units 1 & 2 License Renewal Application - Set 9 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-223, Response to NRC Requests for Additional Information, Set 7, Dated July 27, 2015; and a Correction to Information Associated with the Set 2 Response to RAI 8.2.1.20-2, Related to the Renewal Application2015-08-26026 August 2015 Response to NRC Requests for Additional Information, Set 7, Dated July 27, 2015; and a Correction to Information Associated with the Set 2 Response to RAI 8.2.1.20-2, Related to the Renewal Application Project stage: Response to RAI ML15229A0192015-08-27027 August 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 10 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15217A5412015-08-28028 August 2015 June 9, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 5 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15217A5642015-08-28028 August 2015 June 3, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 4 Pertaining to the LaSalle County Station License Renewal Application (Tac Nos. MF5347 and MF5346) Project stage: RAI ML15217A5752015-08-28028 August 2015 June 10, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 4 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15219A2772015-08-28028 August 2015 June 23, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 6 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15222A0062015-08-28028 August 2015 August 5, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 9 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15195A3382015-08-28028 August 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application-Set 8 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15222A0082015-08-28028 August 2015 July 22, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 8 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15222A0152015-08-28028 August 2015 July 8, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 7 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15224A9352015-08-28028 August 2015 August 11, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 9 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15244B3532015-09-14014 September 2015 RAI for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 11 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-232, Response to NRC Requests for Additional Information, Set 9, Dated August 18, 2015 Related to the License Renewal Application2015-09-15015 September 2015 Response to NRC Requests for Additional Information, Set 9, Dated August 18, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-238, Response to NRC Requests for Additional Information, Set 10, Dated August 27, 2015 Related to License Renewal Application2015-09-17017 September 2015 Response to NRC Requests for Additional Information, Set 10, Dated August 27, 2015 Related to License Renewal Application Project stage: Response to RAI ML15196A1152015-09-22022 September 2015 Aging Management Programs Audit Report Regarding Lasalle County Station, Units 1 and 2, Project stage: Other ML15196A0452015-09-22022 September 2015 Aging Management Programs Audit Report Regarding Lasalle County Station, Units 1 and 2, (TAC Nos. MF5347 and MF5346). Cover Letter Project stage: Other RS-15-239, Response to NRC Requests for Additional Information, Set 8, Dated August 28, 2015 Related to the License Renewal Application2015-09-28028 September 2015 Response to NRC Requests for Additional Information, Set 8, Dated August 28, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-256, Response to NRC Request for Additional Information, Set 11, Dated September 14, 2015 Related to the License Renewal Application2015-10-0808 October 2015 Response to NRC Request for Additional Information, Set 11, Dated September 14, 2015 Related to the License Renewal Application Project stage: Response to RAI ML15208A0522015-10-22022 October 2015 Schedule Revision for the Review of the Lasalle County Station License Renewal Application (TAC Nos. MF5347 & MF5346) Project stage: Approval ML15271A0212015-10-23023 October 2015 Requests for Additional Information for the Review of the Lasalle County Station, Units 1 and 2 License Renewal Application-Set 12 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-281, Response to NRC Requests for Additional Information, Set 12, Dated October 23, 2015 Related to the License Renewal Application2015-10-29029 October 2015 Response to NRC Requests for Additional Information, Set 12, Dated October 23, 2015 Related to the License Renewal Application Project stage: Response to RAI ML15300A3662015-11-0303 November 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 13 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-305, Corrections to the License Renewal Application Dated December 9, 20142015-12-0202 December 2015 Corrections to the License Renewal Application Dated December 9, 2014 Project stage: Other RS-15-306, Submittal of 10 CFR 54.21(b) Annual Amendment to the License Renewal Application2015-12-0202 December 2015 Submittal of 10 CFR 54.21(b) Annual Amendment to the License Renewal Application Project stage: Other RS-15-292, Response to NRC Requests for Additional Information, Set 13, Dated November 3, 2015 Related to the License Renewal Application2015-12-10010 December 2015 Response to NRC Requests for Additional Information, Set 13, Dated November 3, 2015 Related to the License Renewal Application Project stage: Response to RAI ML15272A4002015-12-11011 December 2015 Summary of Teleconference Held on September 24, 2015, Between the NRC and Exelon Generation Co., LLC, Concerning RAI Set 10 Response Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15301A1892015-12-14014 December 2015 Request for Additional Information for the Review of the LaSalle County Station, Units 1 & 2 License Renewal Application - Set 14 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-16-003, Responses to NRC Requests for Additional Information, Set 14, Dated December 14, 2015, and Two Additional Commitment Implementation Schedule Clarifications, Related to the License Renewal Application2016-01-0707 January 2016 Responses to NRC Requests for Additional Information, Set 14, Dated December 14, 2015, and Two Additional Commitment Implementation Schedule Clarifications, Related to the License Renewal Application Project stage: Response to RAI ML15357A2812016-01-0707 January 2016 Summary of Teleconference Held on December 22, 2015, Between the NRC and Exelon Generation Co., LLC, Concerning the LaSalle County Station License Renewal Application (Tac Nos. MF5347 and MF5346) Project stage: Meeting RS-16-007, Supplemental Information Associated with Implementation of BWRVIP-25, Core Plate Inspection and Flaw Evaluation Guidelines, Related to the License Renewal Application2016-01-14014 January 2016 Supplemental Information Associated with Implementation of BWRVIP-25, Core Plate Inspection and Flaw Evaluation Guidelines, Related to the License Renewal Application Project stage: Supplement ML16021A3252016-01-29029 January 2016 Summary of Teleconference Held on January 21, 2016, Between the NRC and Exelon Generation Co., LLC, Concerning RAI 4.2.10-1 Response Project stage: RAI RS-16-033, Update to Commitment 47 Related to the License Renewal Application2016-02-0101 February 2016 Update to Commitment 47 Related to the License Renewal Application Project stage: Other ML15344A3542016-02-16016 February 2016 Requests for Additional Information for the Review of the Lasalle County, Units 1 and 2 License Renewal Application Set 15 (TAC Nos. MF5347 and MF5346) Project stage: RAI 2015-07-16
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Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination 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 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report IR 05000373/20234012023-11-0707 November 2023 County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401 RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000374/20230102023-10-11011 October 2023 NRC Inspection Report 05000374/2023010 IR 05000373/20233012023-09-15015 September 2023 Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212A9012023-08-0303 August 2023 Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report IR 05000373/20230022023-08-0101 August 2023 County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis ML23192A5272023-07-12012 July 2023 NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 ML23186A2062023-07-0606 July 2023 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010 ML23181A1502023-06-30030 June 2023 Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000373/20230112023-06-26026 June 2023 County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167A0352023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel ML23171A9562023-06-12012 June 2023 Post Exam Ltr RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000373/20230012023-05-10010 May 2023 County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001 ML23123A2202023-05-0303 May 2023 Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23121A1612023-05-0101 May 2023 Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23107A1822023-04-18018 April 2023 Operator Licensing Examination Approval Lasalle County Station, May 2023 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000373/20220062023-03-0101 March 2023 Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006) RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station ML23024A1372023-02-0303 February 2023 Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2 ML23031A1972023-01-31031 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011 IR 05000373/20220042023-01-31031 January 2023 County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 2024-01-05
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Text
Exelon Generation RS-16-007 January 14, 2016 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Michael P. Gallagher Vice President.
License Renewal Exelon Nuclear 200 Exelon Way Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54
Subject:
Supplemental information associated with implementation of BWRVIP-25, "Core Plate Inspection and Flaw Evaluation Guidelines," related to the LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5347 AND MF5346)"
References:
- 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon) to NRC Document Control Desk, dated December 9, 2014, "Application for Renewed Operating Licenses" 2. Teleconference Summary from Jeffrey S. Mitchell, USNRC, dated January 7, 2016, "Summary of Teleconference held on December 22, 2015, between the NRC and Exelon Generation Co., LLC, concerning the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346)" In Reference 1, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the LaSalle County Station (LSCS), Units 1 and 2. Reference 2 summarizes a conference call that was held between NRC and Exelon staff personnel on December 22, 2015, related to information contained in the LSCS LRA associated with aging management of core plate rim hold-down bolts. As a result of the change in status of a BWRVIP-25 Deviation Disposition for LSCS, and also as a result of feedback from NRC staff related to aging management of the core plate rim down bolts, Exelon is supplementing the LRA. This Supplement updates various sections of the LRA, and includes the addition of a new Enhancement to the BWR Vessel Internals (B.2.1.9) program commitment (Commitment
- 9) to provide assurance that the function of the core plate rim hold-down bolts is maintained throughout the period of extended operation.
January 14, 2016 U.S. Nuclear Regulatory Commission Page 2 Enclosure A provides a description of this LRA Supplement.
Enclosure B contains updates to sections of the LRA (except for the License Renewal Commitment List) affected by this LRA Supplement.
Enclosure C provides an update to the License Renewal Commitment List (LRA Appendix A, Section A.5). There are no other new or revised regulatory commitments contained in this letter. If you have any questions, please contact Mr. John Hufnagel, Licensing Lead, LaSalle License Renewal Project, at 610-765-5829. I declare under penalty of perjury that the foregoing is true and correct. Executed on /-/6( _. 2 ()/ b Respectfully, Vice President
-License Renewal Projects Exelon Generation Company, LLC
- A. Description of LSCS LRA Supplement B. LSCS License Renewal Application Updates C. LSCS License Renewal Commitment List Update cc: Regional Administrator-NRC Region Ill NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Project Manager, NRR-DORL-LaSalle County Station NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency -Division of Nuclear Safety RS-16-007 Enclosure A Page 1 of 1 Enclosure A Description of LSCS LRA Supplement Related to Core Plate Rim Hold-Down Bolts This enclosure provides a description of an enhancement that is added to the BWR Vessel Internals (B.2.1.9) aging management program and associated revisions to the License Renewal Application (LRA).
As a result of recent change in status of a Deviation Disposition from the inspection guidance within BWRVIP-25 for LSCS Units 1 and 2, and also as a result of feedback from NRC staff related to aging management of the core plate rim hold-down bolts, Exelon is supplementing the LRA. As discussed in LRA Appendix C, Applicant Action Item BWRVIP-25 (5), Exelon had a BWRVIP Deviation Disposition in place, effective until December 31, 2015, to deviate from the inspection guidance within BWRVIP-25 for core plate rim hold-down bolts. The BWRVIP recognizes that it is not possible to implement meaningful inspections using the inspection methods recommended within BWRVIP-25. As of December 31, 2015, the BWRVIP had not developed a NRC-approved revised inspection met hod or other solution for aging management of the core plate rim hold-down bolts. As a result, Exelon revised the Deviation Disposition prior to December 31, 2015 to postpone inspections of the core plate rim hold-down bolts on LSCS Units 1 and 2 until revised BWRVIP guidance for core plate bolting inspection is approved by the NRC, or some other NRC-approved solution is implemented. To ensure adequate aging management of the core plate rim hold-down bolts during the period of extended operation, an enhancement is added to the BWR Vessel Internals aging management program to install core plate wedges no later than six months prior to entering the period of extended operation, or submit an inspection plan for the core plate rim hold-down bolts with supporting analysis for NRC approval at least 2 years prior to entering the period of extended operation. The installation of core plate wedges would eliminate the need to inspect core plate rim hold-down bolts.
This Supplement updates several sections of the LRA, and includes the addition of a new enhancement to the BWR Vessel Internals program commitment (Commitment 9) to provide assurance that the function of the core plate rim hold-down bolts is maintained throughout the period of extended operation.
LRA Section A.2.1.9 is revised to add the enhancement to the BWR Vessel Internals program as shown in Enclosure B. LRA Section B.2.1.9 is revised to add the enhancement to the BWR Vessel Internals program and clarify aging management of the core plate rim hold-down bolts during the period of extended operation, as shown in Enclosure B. LRA Appendix C, Applicant Action Item BWRVIP-25 (5), is revised to be consistent with the current Deviation Disposition from BWRVIP-25 inspection guidance and refer to the added enhancement, as shown in Enclosure B.
LRA Table A.5, Commitment 9 is revised to add Enhancement 4 to the BWR Vessel Internals program as shown in Enclosure C.
RS-16-007 Enclosure B Page 1 of 5 Enclosure B LSCS License Renewal Application Updates Resulting from the Supplement Associated with the Core Plate Rim Hold-Down Bolts
Note: To facilitate understanding, portions of the LRA have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Changes are highlighted with bolded italics for inserted text and strikethroughs for deleted text.
RS-16-007 Enclosure B Page 2 of 5 LRA Appendix A, Section A.2.1.9, starting on page A-13, is revised to add Enhancement 4, as shown below.
A.2.1.9 BWR Vessel Internals The BWR Vessel Internals aging management program is an existing condition monitoring and mitigative program that manages the effects of cracking, loss of material, and loss of fracture toughness of reactor pressure vessel internal components through condition monitoring activiti es that consist of examinations that are implemented through station procedures consistent with the recommendations of the BWRVIP guidelines and ASME Code,Section XI, Table IWB-2500-1. The program also addresses aging degradation of X-750 alloy that is used for BWR vessel internal components. The program also mitigates these aging effects by managing water chemistry per the Water Chemistry (A.2.1.2) program.
The program will include aging management of reactor internal components fabricated from Cast Austenitic Stainless Steel (CASS) for loss of fracture toughness due to thermal aging and neutron embrittlement.
The BWR Vessel Internals aging management program will be enhanced to:
- 1. Perform an assessment of the susceptibility of reactor vessel internal components fabricated from CASS to loss of fracture toughness due to thermal aging embrittlement. If material properties cannot be determined to perform the screening, they will be assumed susceptible to thermal aging for the purposes of determining
program examination requirements.
- 2. Perform an assessment of the susceptibility of reactor vessel internal components fabricated from CASS to loss of fracture toughness due to neutron irradiation embrittlement.
- 3. Specify the required periodic inspection of CASS components determined to be susceptible to loss of fracture toughness due to thermal aging and neutron irradiation embrittlement. The initial inspections will be performed either prior to or within five years after entering the period of extended operation.
- 4. Install core plate wedges no later than six months prior to the period of extended operation, or before the end of the last refueling outage prior to the period of extended operation, whichever occurs later; or, submit an inspection plan for the core plate rim hold-down bolts with a supporting analysis for NRC approval at least 2 years prior to entering the period of extended operation.
These enhancements will be implemented prior to the period of extended operation.
RS-16-007 Enclosure B Page 3 of 5 The fifth paragraph of the Program Description Section of LRA Appendix B Section B.2.1.9, on LRA page B-44, is revised as shown below.
B.2.1.9 BWR Vessel Internals Program Description Core Plate:
Core plate wedges will be installed or i Inspections of the core plate rim hold-down bolts will be performed in accordance with a staff-approved inspection plan.
The installation of core plate wedges would eliminate the need to inspect the core plate rim hold-down bolts.
and f Flaw evaluations are performed in accordance with BWRVIP-25. The repair design criteria in BWRVIP-50-A would be utilized in preparing a repair plan for the core plate.
RS-16-007 Enclosure B Page 4 of 5 The Enhancements subsection of LRA Appendix B, Section B.2.1.9, on LRA page B-46 is revised to add Enhancement 4, as shown below.
B.2.1.9 BWR Vessel Internals Enhancements Prior to the period of extended operation, the following enhancements will be implemented in the following program elements:
- 1. Perform an assessment of the susceptibility of reactor vessel internal components fabricated from CASS to loss of fracture toughness due to thermal aging embrittlement. If material properties cannot be determined to perform the screening, they will be assumed susceptible to thermal aging for the purposes of determining
program examination requirements.
Program Elements Affected: Scope of Program (Element 1) and Acceptance Criteria (Element 6)
- 2. Perform an assessment of the susceptibility of reactor vessel internal components fabricated from CASS to loss of fracture toughness due to neutron irradiation embrittlement. Program Element Affected: Scope of Program (Element 1)
- 3. Specify the required periodic inspection of CASS components determined to be susceptible to loss of fracture toughness due to thermal aging and neutron irradiation embrittlement. The initial inspection will be performed either prior to or within five years after entering the period of extended operation. Program Elements Affected: Parameters Monitored/Inspected (Element 3), Detection of Aging Effects (Element 4), and Acceptance Criteria (Element 6)
- 4. Install core plate wedges no later than six months prior to the period of
extended operation, or before the end of the last refueling outage prior to the period of extended operation, whichever occurs later; or, submit an inspection plan for the core plate rim hold-down bolts with a supporting analysis for NRC approval at least 2 years prior to entering the period of extended operation. Program Element Affected: Scope of Program (Element 1)
RS-16-007 Enclosure B Page 5 of 5 LRA Appendix C, Applicant Action Item BWRVIP-25 (5) on LRA page C-4 is revised to update the disposition of the Applicant Action Item, as shown below. BWRVIP-25 Core Plate Inspection and Flaw Evaluation Guidelines Action Item Description LaSalle Response BWRVIP-25 (4)
Due to susceptibility of the rim hold-down bolts to stress relaxation, applicants referencing the BWRVIP-25
report for license renewal should
identify and evaluate the projected stress relaxation as a potential TLAA issue. Preload of the rim hold-down bolts is required to prevent lateral motion of the core plate for those plants that do not have core plate wedges installed.
Stress relaxation of the RPV core plate rim hold-down bolts has been identified as a TLAA issue as evaluated in LRA Section 4.2.8.
BWRVIP-25 (5)
Until such time as an expanded technical basis for not inspecting the rim hold-down bolts is approved by the staff, applicants referencing the BWRVIP-25 report for license renewal should continue to perform inspections of the rim hold-down bolts. The BWRVIP recognizes that it is not possible to implement meaningful inspections using the inspection methods recommended in BWRVIP-25. The BWRVIP is addressing this issue and intends to develop revised guidance.
The BWRVIP recommendation to document deviation from BWRVIP-25 inspection guidelines of the core plate hold down bolts is currently being implemented. A BWRVIP Deviation Disposition is in place December 31, 2015, or until the NRC approves revised BWRVIP guidance for core plate bolting inspection within BWRVIP, or some other NRC-approved solution is implemented , whichever occurs first. Therefore, inspection of the core plate rim hold down bolts will be in compliance with BWRVIP guidance prior to and through the period of extended operation. BWR Vessel Internals aging management program Enhancement 4 requires installation of core plate wedges no later than six months prior to entering the period of extended operation, or submittal of an
inspection plan for the core plate rim hold-
down bolts with a supporting analysis for NRC approval at least 2 years prior to entering the period of extended operation. The installation of core plate wedges would eliminate the need to inspect the core plate rim hold-down bolts.
RS-16-007 Enclosure C Page 1 of 2 Enclosure C LSCS License Renewal Commitment List Update This Enclosure identifies commitments made in this document and is an update to the LSCS LRA Appendix A, Table A.5 License Renewal Commitment List. Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the
NRC's information and are not regulatory commitments.
Changes to the LSCS LRA Appendix A, Table A.5 License Renewal Commitment List are as a result of this LRA Supplement, pertaining to the core plate rim hold-down bolts.
To facilitate understanding, relevant portions of the previously submitted License Renewal Commitment List have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Additions due to this submittal are highlighted with bolded italics for inserted text.
RS-16-007 Enclosure C Page 2 of 2 LRA Table A.5, License Renewal Commitment List, Commitment 9 on page A-61, is revised to include the added commitment, as shown below.
NO. PROGRAM OR TOPIC COMMITMENT IMPLEMENTATION SCHEDULE SOURCE 9 BWR Vessel Internals BWR Vessel Internals is an existing program that will be enhanced to:
- 1. Perform an assessment of the susceptibility of reactor vessel internal components fabricated from CASS to loss of fracture toughness due to thermal aging embrittlement. If material properties cannot be determined to perform the screening, they will be assumed susceptible to thermal aging for the purposes of determining program examination requirements.
- 2. Perform an assessment of the susceptibility of reactor vessel internal components fabricated from CASS to loss of fracture toughness due to neutron irradiation embrittlement.
- 3. Specify the required periodic inspec tion of CASS components determined to be susceptible to loss of fracture toughness due to thermal aging and neutron irradiation embrittlement. The initial inspections will be performed either prior to or within five years after entering the period of extended operation.
- 4. Install core plate wedges no later than six months prior to the period of extended operation, or before the end of the last refueling outage prior to the period of extended operation, whichever occurs later; or, submit an inspection plan for the core plate rim hold-down bolts with a supporting analysis for NRC approval at least 2 years prior to entering the period of extended operation.
Program to be enhanced no later than six months prior to the period of extended operation.
Additional schedule information identified in commitment.
Section A.2.1.9 Exelon Letter RS-16-007 01/14/2016