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| | number = ML14065A528 | | | number = ML14065A528 |
| | issue date = 04/15/2014 | | | issue date = 04/15/2014 |
| | title = Limerick Generating Station, Units 1 and 2 - Relaxation of Certain Scheduler 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 | | | title = Relaxation of Certain Scheduler 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 |
| | author name = Leeds E J | | | author name = Leeds E |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000352, 05000353 | | | docket = 05000352, 05000353 |
| | license number = | | | license number = |
| | contact person = Bamford P J, NRR/DORL, 415-2833 | | | contact person = Bamford P, NRR/DORL, 415-2833 |
| | case reference number = EA-12-049 | | | case reference number = EA-12-049 |
| | document type = Letter | | | document type = Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation | | {{#Wiki_filter: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 |
| : Company, LLC 4300 Winfield Road Warrenville, IL 60555 April15, 2014
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| ==SUBJECT:== | | ==SUBJECT:== |
| | LIMERICK GENERATING STATION, UNITS 1 AND 2- RELAXATION OF CERTAIN SCHEDULAR 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" |
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| LIMERICK GENERATING
| | ==Dear Mr. Pacilio:== |
| : STATION, UNITS 1 AND 2-RELAXATION OF CERTAIN SCHEDULAR 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" | |
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| ==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 Limerick Generating Station (LGS), 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 LGS, 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-13-1 09, Phase I (wetwell vent), extend beyond those of Order EA-12-049 for LGS, 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 26, 2014 (ADAMS Accession No. ML14057A551 ), the licensee requested relief from the final compliance dates of Order EA 049. Specifically, the licensee requested an extension of one refueling cycle for LGS, 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 LGS Unit 1, to the completion of the spring 2018 refueling |
| | |
| | M. Pacilio outage. For LGS 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 26, 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-13-1 09 is implemented, LGS 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 LGS, Unit 1, and the completion of the spring 2017 refueling outage for LGS, 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 Peter Bamford at 301-415-2833. |
| | Eric J. eeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 cc: Listserv |
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| By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12054A735),
| | ML14065A528 OFFICE NRR/MSD/MSPB/PM NRR/MSD/MSPB/LA NRR/MSD/MRSB/BC NRR/MSD/MSPB/BC NAME PBamford Slent SWhaley JBowen DATE 03/06/14 03/07/14 03/10/14 03/14/14 OFFICE OE OGC MSD/0 NRR/0 NAME RFretz CHair JDavis Eleeds DATE 03/18/14 03/25/14 03/30/14 04/15/14}} |
| the U.S. Nuclear Regulatory Commission (NRC) ordered Exelon Generation
| |
| : Company, LLC (Exelon, the licensee) to take certain actions at Limerick Generating Station (LGS), 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. ML 12054A694),
| |
| the NRC ordered Exelon to install a reliable hardened containment vent system at LGS, Units 1 and 2, via Order EA-12-050.
| |
| By letter dated June 6, 2013 (ADAMS Accession No. ML 13143A321),
| |
| 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-13-1 09, Phase I (wetwell vent), extend beyond those of Order EA-12-049 for LGS, 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 26, 2014 (ADAMS Accession No. ML 14057 A551 ), the licensee requested relief from the final compliance dates of Order EA-12-049. Specifically, the licensee requested an extension of one refueling cycle for LGS, 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 LGS Unit 1, to the completion of the spring 2018 refueling M. Pacilio outage. For LGS 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 26, 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-13-1 09 is implemented, LGS 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 LGS, Unit 1, and the completion of the spring 2017 refueling outage for LGS, 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 Peter Bamford at 301-415-2833.
| |
| Eric J. eeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 cc: Listserv M. Pacilio outage. For LGS 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 26, 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-13-1 09 is implemented, LGS 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-13-109.
| |
| 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 LGS, Unit 1, and the completion of the spring 2017 refueling outage for LGS, 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 Peter Bamford at 301-415-2833.
| |
| Sincerely, IRA/ Eric J. Leeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 cc: Listserv DISTRIBUTION:
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| PUBLIC LPLI-2 Reading RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl1-2 Resource RidsNrrPMLimerick Resource RidsRgn1 Mail Center Resource RidsNrrLASLent Resource ADAMS Accession No.: ML 14065A528 OFFICE NRR/MSD/MSPB/PM NRR/MSD/MSPB/LA NRR/MSD/MRSB/BC NAME PBamford Slent SWhaley DATE 03/06/14 03/07/14 03/10/14 OFFICE OE OGC MSD/0 NAME RFretz CHair JDavis DATE 03/18/14 03/25/14 03/30/14 OFFICIAL RECORD COPY NRR/MSD/MSPB/BC JBowen 03/14/14 NRR/0 Eleeds 04/15/14}}
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Category:Letter
MONTHYEARML24243A0482024-09-19019 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 IR 05000352/20240022024-08-12012 August 2024 Integrated Inspection Report 05000352/2024002 and 05000353/2024002 ML24220A2392024-08-12012 August 2024 Correction to Technical Specification Page 3/4 3-11 in Amendment No. 225 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 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 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 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 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 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 IR 05000352/20240012024-05-0707 May 2024 Integrated Inspection Report 05000352/2024001 and 05000353/2024001 ML24124A0432024-05-0303 May 2024 Response to Requests for Additional Information (RAIs 9 Through 14) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with 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 ML24114A3222024-04-23023 April 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) - Pivot to Unit ML24109A0702024-04-18018 April 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFRC50.52 ATWS Rule to Support the Digital Modernization Project Installation . ML24093A0912024-04-17017 April 2024 Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24106A1832024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases 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 ML24096A1372024-04-0505 April 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Limerick Generating Station – Holtec MPC-89CBS 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 IR 05000352/20244012024-03-19019 March 2024 Security Baseline Inspection Report 05000352/2024401 and 05000353/2024401 IR 05000352/20240102024-03-18018 March 2024 Biennial Problem Identification and Resolution Inspection Report 05000352/2024010 and 05000353/2024010 ML24078A2752024-03-18018 March 2024 Response to Requests for Additional Information (RAIs 5, 6, 7, and 8) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog ML24067A2942024-03-0707 March 2024 Response to Requests for Additional Information (RAI 4, RAI 1.c Revision) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related. IR 05000352/20230062024-02-28028 February 2024 Annual Assessment Letter for Limerick Generating Station, Units 1 and 2 (Reports 05000352/2023006 and 05000353/2023006) ML24057A4272024-02-26026 February 2024 Response to Requests for Additional Information (RAIs 1, 2, and 3) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves 2024-09-06
[Table view] |
Text
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:
LIMERICK GENERATING STATION, UNITS 1 AND 2- RELAXATION OF CERTAIN SCHEDULAR 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 Limerick Generating Station (LGS), 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 LGS, 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-13-1 09, Phase I (wetwell vent), extend beyond those of Order EA-12-049 for LGS, 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 26, 2014 (ADAMS Accession No. ML14057A551 ), the licensee requested relief from the final compliance dates of Order EA 049. Specifically, the licensee requested an extension of one refueling cycle for LGS, 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 LGS Unit 1, to the completion of the spring 2018 refueling
M. Pacilio outage. For LGS 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 26, 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-13-1 09 is implemented, LGS 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 LGS, Unit 1, and the completion of the spring 2017 refueling outage for LGS, 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 Peter Bamford at 301-415-2833.
Eric J. eeds, Director Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 cc: Listserv
ML14065A528 OFFICE NRR/MSD/MSPB/PM NRR/MSD/MSPB/LA NRR/MSD/MRSB/BC NRR/MSD/MSPB/BC NAME PBamford Slent SWhaley JBowen DATE 03/06/14 03/07/14 03/10/14 03/14/14 OFFICE OE OGC MSD/0 NRR/0 NAME RFretz CHair JDavis Eleeds DATE 03/18/14 03/25/14 03/30/14 04/15/14