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MONTHYEARML15106A0132015-04-29029 April 2015 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. Project stage: Approval 2015-04-29
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Category:Letter
MONTHYEARML24318A9432024-11-13013 November 2024 – Notification of Conduct of Phase II Inspection of Title 10 of the Code of Federal Regulations 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactor ML24310A0062024-11-0808 November 2024 – Acceptance of Requested Licensing Action Modification to Technical Specifications 3.6.1.2 and Main Stem Isolation Valve Leakage Requirements Amendment IR 05000352/20240032024-11-0808 November 2024 Integrated Inspection Report 05000352/2024003 and 05000353/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24151A3842024-10-31031 October 2024 – Issuance of Amendment Nos. 264 and 226 Support to Digital Modernization Project Installation (EPID L-2023-LLA-0025) and Exemption from the Requirements of 10 CFR 50.62 ML24303A0902024-10-29029 October 2024 Operator Licensing Examination Approval ML24303A2782024-10-29029 October 2024 10 CFR 50.46 Annual Report ML24299A2642024-10-25025 October 2024 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications IR 05000352/20240122024-10-17017 October 2024 Commercial Grade Dedication Inspection Report 05000352/2024012 and 05000353/2024012 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 ML24274A2372024-10-0707 October 2024 – Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications ML24278A3022024-10-0404 October 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A0032024-09-27027 September 2024 Generation Station, Units 1 and 2 – Regulatory Audit Plan Supporting Review of the Component Interface Module System of the Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) (Redacted) ML24243A0482024-09-19019 September 2024 Generation Station, Unit Nos. 1 and 2 - Schedule Update for License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24215A4042024-09-18018 September 2024 Request for Withholding Information from Public Disclosure IR 05000352/20244202024-09-16016 September 2024 – Security Baseline Inspection Report 05000352/2024420 and 05000353/2024420 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 IR 05000352/20250102024-09-10010 September 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000352/2025010 and 05000353/2025010 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000352/20230022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000352/2023002 and 05000353/2023002 IR 05000352/20240052024-08-29029 August 2024 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2024005 and 05000353/2024005) ML24241A1952024-08-28028 August 2024 License Amendment Request for Modification to Technical Specification 3.6.1.2 and Main Steam Isolation Valve Leakage Rate Requirements ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24163A3902024-08-14014 August 2024 Request for Withholding Information from Public Disclosure ML24220A2392024-08-12012 August 2024 Correction to Technical Specification Page 3/4 3-11 in Amendment No. 225 IR 05000352/20240022024-08-12012 August 2024 Integrated Inspection Report 05000352/2024002 and 05000353/2024002 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 ML24204A0712024-07-29029 July 2024 Issuance of Amendment Nos. 263 and 225 Technical Specifications for Main Steam Line Tunnel Temperature ML24208A1592024-07-25025 July 2024 Regulatory Audit Plan Supporting Review of the System Development Portion of Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) - Non-Proprietary ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24201A1662024-07-19019 July 2024 Response to Request for Additional Information for License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam L ML24199A1842024-07-15015 July 2024 RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24180A1572024-06-28028 June 2024 Request to Return and Replace WEC Documents (EQ-EV-386-GLIM, EQ-QR- 433-GLIM, and APP-GW-GLR-611), to Meet 10CFR2.390 Request to Withdraw from Public Disclosure Requirements ML24170A7702024-06-20020 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, Opportunity for Hearing(Epid L-2024-LLA-0079) LTR 05000352/LER-2024-003, Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK1232024-06-18018 June 2024 Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK123 ML24166A1142024-06-14014 June 2024 Response to Requests for Additional Information (RAIs 15 Through 23) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems 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 ML24165A2642024-06-13013 June 2024 License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam Line Tunnel Temperature TS 3/4.7.9 05000352/LER-2024-002, Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker2024-06-10010 June 2024 Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker 05000352/LER-2024-001, Leakage for the Unit 1 `B Outboard Main Steam Isolation Valve Exceeded Technical Specification Limit2024-06-10010 June 2024 Leakage for the Unit 1 `B Outboard Main Steam Isolation Valve Exceeded Technical Specification Limit ML24151A2882024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24151A2012024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24150A0242024-05-29029 May 2024 Notification of Commercial Grade Dedication Inspection (05000352/2024012 and 05000353/2024012) and Request for Information ML24149A2112024-05-28028 May 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000352/20243022024-05-20020 May 2024 Revised Initial Operator Licensing Examination Report 05000352/2024302 and 05000353/2024302 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report 2024-09-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 29, 2015 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNIT 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" (TAC NO. MF6062)
Dear Mr. Hanson:
By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12054A735), the U.S. Nuclear Regulatory Commission (NRC) ordered Exelon Generation Company, LLC (Exelon, the licensee) to take certain actions at Limerick Generating Station (LGS), Unit 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, containment cooling, and spent fuel pool cooling capabilities during beyond-design-basis external events.Section IV of NRC Order EA-12-049 states that licensees proposing to deviate from requirements contained in the order may request that the Director, Office of Nuclear Reactor Regulation, relax or rescind certain requirements. Condition IV.A.2 of NRC Order EA-12-049 requires full implementation of the order requirements no later than two refueling cycles after submittal of the overall integrated plan, or by December 31, 2016, whichever comes first. By letter dated April 15, 2014 (ADAMS Accession No. ML 14065A528), the NRC granted relaxation of certain schedule requirements of Order EA-12-049 related to full containment wetwell venting capability until completion of the spring 2017 refueling outage for LGS, Unit 2, consistent with the requirements of NRC Order EA-13-109, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013 (ADAMS Accession No. ML 13143A334). The NRC relaxation approval dated April 15, 2014 identified that the equipment and modifications required to implement the mitigating strategies required by Order EA-12-049 were to be completed and available for use in accordance with the original implementation schedule requirements, except for the primary containment venting strategy. By letter dated April 2, 2015 (ADAMS Accession No. ML 15092A833), the licensee informed the NRC of its additional LGS, Unit 2, request for schedule relaxation from compliance with Order EA-12-049 for no more than 90 days following restart from the spring 2015 refueling outage. The additional schedule relaxation was requested to allow completion of two FLEX storage robust buildings, located in the LGS site protected areas.
B. Hanson The request dated April 2, 2015, stated that building design and permitting delays associated with the FLEX storage robust buildings resulted in a delay to the construction start date. Additional delays were encountered due to building construction activities continuing into the winter months, where adverse weather conditions further impeded the work progress. The licensee also attributed delays to complications encountered in adapting the Exelon fleet building design to the LGS site specific application that required two separate buildings. The licensee stated that the LGS portable FLEX equipment that will be stored in the completed FLEX storage robust buildings has been procured and is currently located onsite. In addition, the design and programmatic changes required to implement the LGS, Unit 2, mitigating strategies will be completed in accordance with the current requirements of Order EA-12-049, except for the primary containment venting strategy, as discussed above. Therefore, the FLEX mitigating strategy equipment will be onsite and available. The licensee also stated that in order to maintain post-deployment capability, key FLEX equipment, such as large portable generators and pumps, will be stored in locations that provide physical separation during the requested 90-day extension period. The locations will not be susceptible to flooding events or building collapse, minimizing the likelihood of one event impacting both sets of equipment. If hurricane conditions are predicted, one set of portable FLEX equipment will be moved to a protected location. In light of the facts presented in the licensee's April 2, 2015, letter, the NRG staff has determined that the licensee has demonstrated good cause to relax the NRG Order EA-12-049 implementation date for 90 days following restart from the spring 2015 refueling outage. The NRG staff also considered that, following the accident at Fukushima Dai-ichi, the NRG 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. Given the plant-specific circumstances at Limerick, and that implementation of the mitigating strategies relaxed by this letter will be completed before December 2016, the NRG staff approves the requested relaxation. Accordingly, based upon the authority granted to the Director, Office of Nuclear Reactor Regulation, the requirement of implementation of mitigating strategies for LGS, Unit 2, associated with Order EA-12-049 is relaxed until no later than 90 days following restart from the spring 2015 refueling outage. Full compliance with Order EA-12-049 remains relaxed to the completion of the spring 2017 refueling outage for LGS, Unit 2, as granted in NRG letter dated April 15, 2014, to allow the licensee sufficient time to implement a severe accident capable hardened containment wetwell vent.
B. Hanson If you have any questions, please contact John Hughey at 301-415-3204. Docket No. 50-353 cc: Listserv Sincerely, &.11an, Direc,,....t...._o_r Office of Nuclear Reactor Regulation B. Hanson If you have any questions, please contact John Hughey at 301-415-3204. Docket No. 50-353 cc: Listserv DISTRIBUTION: PUBLIC JLD R/F RidsAcrsAcnw_MailCTR Resource Sincerely, IRA/ William M. Dean, Director Office of Nuclear Reactor Regulation RidsNrrDorllpl1-2 Resource RidsNrrPMLimerick Resource RidsRgn1 MailCenter Resource MHalter, NRR ADAMS Accession No.: ML 15106A013 !OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NRR/DORULPL 1-2/PM OE NAME JHughey Slent REnnis RFretz DATE 04/16/15 04/16/15 04/16/15 04/16/15 OFFICE NRR/JLD/JOMB/BC(A) OGC (NLO) NRR/JLD/D NRR/D NAME MHalter DCylkowski JDavis WDean DATE 04/16/15 04/23/15 04/24/15 04/29/15 OFFICIAL RECORD COPY