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Category:Letter
MONTHYEARIR 05000373/20243012024-10-31031 October 2024 Initial License Examination Report 05000373/2024301 05000374/2024301 IR 05000373/20244042024-10-23023 October 2024 County Station – Security Baseline Inspection Report 05000373/2024404 and 05000374/2024404 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests 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 IR 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 05000373/LER-2023-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation2023-12-0404 December 2023 Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation 2024-09-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April15, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2- RELAXATION OF CERTAIN SCHEDULE REQUIREMENTS FOR ORDER EA-12-049 "ISSUANCE OF ORDER TO MODIFY LICENSES WITH REGARD TO REQUIREMENTS FOR MITIGATION STRATEGIES FOR BEYOND DESIGN BASIS EXTERNAL EVENTS"
Dear Mr. Pacilio:
By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12054A735), the U.S. Nuclear Regulatory Commission (NRC) ordered Exelon Generation Company, LLC (Exelon, the licensee) to take certain actions at LaSalle County Station (LaSalle), Units 1 and 2, associated with the Fukushima Near-Term Task Force Recommendations. Order EA-12-049 directed that actions be taken by licensees to develop and implement strategies to maintain or restore core cooling, reactor coolant system inventory, containment cooling, and spent fuel pool cooling capabilities during beyond design basis external events (BDBEEs). By letter dated March 12, 2012 (ADAMS Accession No. ML12054A694), the NRC ordered Exelon to install a reliable hardened containment vent system at LaSalle, Units 1 and 2, via Order EA-12-050. By letter dated June 6, 2013 (ADAMS Accession No. ML13143A321), the NRC superseded the requirements of Order EA-12-050, with Order EA-13-1 09, which requires the installation of reliable hardened containment vents capable of operation under severe accident conditions. The compliance date requirements of Order EA-13-109, Phase I (wetwell vent), extend beyond those of Order EA-12-049 for LaSalle, Units 1 and 2.
Section IV of Order EA-12-049 states that licensees proposing to deviate from requirements of the order may request that the Director, Office of Nuclear Reactor Regulation, relax or rescind certain requirements. By letter dated February 27, 2014 (ADAMS Accession No. ML14059A076), the licensee requested schedule relaxation from the final compliance dates of Order EA-12-049. Specifically, the licensee requested an extension of one refueling cycle for LaSalle, Units 1 and 2, to complete full implementation of the hardened severe accident capable containment wetwell vent. The extension request was proposed because the installation of a containment wetwell vent that meets the requirements of Order EA-13-109, Phase I, will take additional time to complete, as compared to the compliance dates associated with Order EA-12-049.
To allow the time to design and install the severe accident capable hardened containment wetwell vent, and integrate it into the mitigating strategies required for Order EA-12-049, the licensee requests to relax the Order EA-12-049 full implementation date from the completion of the spring 2016 refueling outage for LaSalle Unit 1, to the completion of the spring 2018
M. Pacilio refueling outage. For LaSalle Unit 2, the licensee requests a relaxation from the completion of the spring 2015 refueling outage to the completion of the spring 2017 refueling outage.
In light of the facts presented in the licensee's letter dated February 27, 2014, the NRC staff has determined that the licensee has presented good cause for a relaxation of the order implementation dates. The licensee proposes the equipment and modifications required to implement the mitigating strategies required by Order EA-12-049 will be completed and available for use in accordance with the original implementation schedule requirements, except for the primary containment venting strategy. Until the full containment wetwell venting capability required by Order EA-13-109 is implemented, LaSalle will maintain a containment venting strategy in accordance with existing emergency operating procedures at each unit. By completing the specified plant configuration changes (other than the severe accident capable containment wetwell vent), and maintaining the ability to vent containment in accordance with existing procedures, a portion of the desired increase in capability to respond to a BDBEE will be realized within the timeframe specified in Order EA-12-049. The requested extension allows the licensee sufficient time to install the enhanced containment wetwell vent capability necessary for full Order EA-12-049 compliance within an appropriate amount of time, consistent with the requirements of Order EA-13-1 09. The NRC staff also considered that, following the accident at Fukushima Dai-ichi, the NRC concluded that a sequence of events such as the Fukushima Dai-ichi accident is unlikely to occur in the United States based on the current regulatory requirements and existing plant capabilities. The NRC staff therefore approves the relaxation of the order implementation dates.
Accordingly, based upon the authority granted to the Director, Office of Nuclear Reactor Regulation, the requirement of the order for full implementation is relaxed until the completion of the spring 2018 refueling outage for LaSalle, Unit 1, and the completion of the spring 2017 refueling outage for LaSalle, Unit 2, to allow the licensee sufficient time to implement a severe accident capable hardened containment wetwell vent at each respective unit.
If you have any questions, please contact John Boska at 301-415-2901.
Sincerely,
~~
Eric J Leeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-37 4 cc: Listserv
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