Letter Sequence Approval |
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MONTHYEARML15043A6492015-02-12012 February 2015 Exigent License Amendment Request - Extension of Implementation Period for License Amendment No. 174, Leak Detection System Technical Specification Setpoint, Allowable Value and Design Basis Changes Project stage: Request ML15041A6172015-02-13013 February 2015 Public Notice - NRC Staff Proposes to Amend Operating License at the Limerick Generating Station, Unit 2 Project stage: Request ML15041A6152015-02-13013 February 2015 Public Notice of Application for Amendment to Facility Operating License Project stage: Other ML15054A3082015-02-23023 February 2015 ACE Comments - Limerick, Unit 2, Objection to Exelon'S Requested Amendment of Amendment No. 174, Leak Detection System Setpoint and Allowable Value Changes Project stage: Other ML15049A0842015-02-25025 February 2015 Issuance of Exigent Amendment Extend Implementation Period for Amendment No. 174 - Leak Detection System Setpoint and Allowable Value Changes Project stage: Approval 2015-02-13
[Table View] |
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Category:Letter
MONTHYEARML24151A3842024-10-31031 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 05000352/20240052024-08-29029 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 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 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 ML24151A2882024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24151A2012024-06-10010 June 2024 Request for Withholding Information from Public Disclosure 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 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 . 2024-09-06
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23145A1972023-06-23023 June 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 255, 256, 257, 258, 259, and 260 ML23089A1242023-05-17017 May 2023 Issuance of Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization and Treatment of Structures, Systems a Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component ML22348A1762023-03-0707 March 2023 Issuance of Amendment Nos. 260 and 222 Regarding Technical Specifications 3.3.7.4, Remote Shutdown System Instrumentation and Controls ML22272A0372023-01-0303 January 2023 Issuance of Amendment Nos. 258 and 220 Regarding Technical Specifications 3/4.8.1, AC Sources-Operating and 3/4.5.1, ECCS-Operating ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22003A1862022-02-17017 February 2022 Issuance of Amendment Nos. 256 and 218 Technical Specification Changes Related to Technical Specifications Task Force (TSTF) Traveler 205-A, Revision 3, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21263A2482021-10-0101 October 2021 Audit Plan Supporting LAR Request to Implement Alternate Defense-in-Depth, Pressure Boundary, & Seismic Tier 1 Categorization Process in Accordance with Requirements of 10 CFR 50.69 ML21181A0442021-09-28028 September 2021 Issuance of Amendment Nos. 253 and 215 Technical Specification Changes Related to Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML21032A2702021-02-22022 February 2021 Issuance of Amendment Nos. 252 and 214, Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20255A0632020-12-0101 December 2020 Issuance of Amendment Nos. 250 and 212 Technical Specification Changes Related to Inservice Testing Program of the Safety Relief Valves ML20239A7252020-11-30030 November 2020 Issuance of Amendment Nos. 249 and 211 Adopt TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities ML20160A4592020-08-0707 August 2020 Issuance of Amendment Nos. 248 and 210 Revise Technical Specifications to Support Implementation of 10 CFR 50.69 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20098C9222020-04-0909 April 2020 Issuance of Amendment No. 245 Regarding Technical Specifications Change to Allow a One-Time Increase in Main Steam Isolation Valve Allowable Leakage Rate (EPID L-2020-LLA-0064) (Emergency Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML20034F6372020-02-28028 February 2020 Issuance of Amendment Nos. 240 and 203 to Implement TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19207A0062019-10-0303 October 2019 Issuance of Amendment Nos. 237 and 200 Revise Technical Specifications to Allow Penetration Flow Path Isolation for Inoperable Isolation Actuation Instrumentation ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19036A9132019-02-28028 February 2019 Issuance of Amendment Nos. 234 and 197 Adopt TSTF-372, Revision 4, Addition of LCO 3.0.8, Inoperability of Snubbers ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18255A2782018-11-27027 November 2018 Issuance of Amendment Nos. 232 and 195 to Revise Technical Specifications to Lower the Minimum Standby Liquid Control System Pump Flowrate ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18165A1622018-07-31031 July 2018 Issuance of Amendment Nos. 230 and 193 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components (CAC Nos. MF9873 and MF9874; EPID L-2017-LLA-0275) ML18113A0452018-05-29029 May 2018 Issuance of Amendments to Revise Technical Specification Requirements for Secondary Containment ML18025B7692018-02-28028 February 2018 Issuance of Amendment Nos. 228 and 191 Revising Technical Specifications to Relocate Main Condenser Offgas Monitoring Instrumentation and Gaseous Effluents TSs (CAC Nos. MF9650 and MF9651; EPID L-2017-LLA-0214) ML18017A2012018-02-27027 February 2018 Issuance of Amendment Nos. 227 and 190 Revising Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC Nos. MF9967 and MF9968; EPID L-2017-LLA-0260) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML17103A0812017-05-16016 May 2017 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-545 ML17024A0892017-03-29029 March 2017 Issuance of Amendments Safety Limit Minimum Critical Power Ratio Change ML17047A3532017-03-15015 March 2017 Issuance of Amendment Partial Length Fuel Rod Burnup ML16356A2722017-02-28028 February 2017 Issuance of Amendments to Revise High Pressure Coolant Injection System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications ML16335A0382016-12-29029 December 2016 Issuance of Amendments to Revise Technical Specification Snubber Requirements ML16307A0122016-12-0505 December 2016 Correction to Amendment No. 185 Regarding Application of an Alternative Source Methodology ML16041A0212016-03-15015 March 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML15356A1402016-01-28028 January 2016 Issuance of Amendments Secondary Containment Access Openings ML15218A5012015-09-15015 September 2015 Issuance of Amendment Nos. 219 and 181 Proposed Change to Add New Limiting Conditions for Operation 3.0.5 and 3.0.6 ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 2024-05-23
[Table view] Category:Safety Evaluation
MONTHYEARML24204A0712024-07-29029 July 2024 Issuance of Amendment Nos. 263 and 225 Technical Specifications for Main Steam Line Tunnel Temperature ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23089A1242023-05-17017 May 2023 Issuance of Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization and Treatment of Structures, Systems a Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component ML23094A1792023-05-17017 May 2023 Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization & Treatment of Structures, Systems, Components for NPR & Denial of Proposed Alternative Defense in Depth & Pressure Boundary Component-Partial Denial SE Encl 4 ML23094A1712023-05-17017 May 2023 Amd Nos. 261 & 223 Alternate Seismic Approach for Risk-Informed Categorization & Treatment of Structures, Systems and Components for NPR and Denial Proposed Alternative Defense in Depth and Pressure Boundary Component ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22348A1762023-03-0707 March 2023 Issuance of Amendment Nos. 260 and 222 Regarding Technical Specifications 3.3.7.4, Remote Shutdown System Instrumentation and Controls ML23005A0082023-02-23023 February 2023 Technical Specifications to Correct Non-conservative Technical Specification Table 3.3.2-1 for Main Steam Line Isolation Trip Function 1.G (EPID L 2020 Lla 0034) Amds. 259 and 221 ML22272A0372023-01-0303 January 2023 Issuance of Amendment Nos. 258 and 220 Regarding Technical Specifications 3/4.8.1, AC Sources-Operating and 3/4.5.1, ECCS-Operating ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22003A1862022-02-17017 February 2022 Issuance of Amendment Nos. 256 and 218 Technical Specification Changes Related to Technical Specifications Task Force (TSTF) Traveler 205-A, Revision 3, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21181A0442021-09-28028 September 2021 Issuance of Amendment Nos. 253 and 215 Technical Specification Changes Related to Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21172A2682021-09-0202 September 2021 Issuance of Relief Request I4r-24 Associated with Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations for the Remainder of the Fourth 10-Year Isi Interval and Up to the End of the 60-Year Operating License ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21032A2702021-02-22022 February 2021 Issuance of Amendment Nos. 252 and 214, Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20322A0092020-12-10010 December 2020 Issuance of Alternative Requests 41-VRR-8 and 41-VRR-7 Regarding Certain Inservice Testing Program Requirements for Safety Relief Valves ML20255A0632020-12-0101 December 2020 Issuance of Amendment Nos. 250 and 212 Technical Specification Changes Related to Inservice Testing Program of the Safety Relief Valves ML20239A7252020-11-30030 November 2020 Issuance of Amendment Nos. 249 and 211 Adopt TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20280A7572020-11-0505 November 2020 Revised Safety Evaluation of Relief Requests GVRR-8, 11 PRR-1, 90 PRR-1, and 47 VRR-2 Regarding the Fourth 10-Year Interval of the Inservice Testing Program (EPID L-2018-LLR-0384 Through EPID L-2018-LLR-0387) ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20160A4592020-08-0707 August 2020 Issuance of Amendment Nos. 248 and 210 Revise Technical Specifications to Support Implementation of 10 CFR 50.69 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20090B4102020-06-0202 June 2020 Issuance of Relief Request GVRR-9 Associated with Pandemic-Related Issues - Inservice Testing Interval Extension for Motor Operated Valves (EPID L-2020-LLR-0046 (COVID-19)) ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20089A0012020-04-20020 April 2020 Issuance of Relief Request I4R-23 Associated with Pandemic-Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) (EPID L-2020-LLR-0044 (COVID-19)) ML20098C9222020-04-0909 April 2020 Issuance of Amendment No. 245 Regarding Technical Specifications Change to Allow a One-Time Increase in Main Steam Isolation Valve Allowable Leakage Rate (EPID L-2020-LLA-0064) (Emergency Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034F6372020-02-28028 February 2020 Issuance of Amendment Nos. 240 and 203 to Implement TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19207A0062019-10-0303 October 2019 Issuance of Amendment Nos. 237 and 200 Revise Technical Specifications to Allow Penetration Flow Path Isolation for Inoperable Isolation Actuation Instrumentation ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19099A2632019-04-22022 April 2019 Issuance of Relief Request 14R-08, Revision 1, Regarding Pressure Testing of Containment Atmospheric Control Penetration Piping ML19099A3072019-04-16016 April 2019 Issuance of Relief Request 14R-18 Associated with Inaccessible Supports for the Fourth 10-Year Inservice Inspection Interval Pipping 2024-07-29
[Table view] |
Text
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 0
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- 1) * '*w*" ~o February 25, 2015
Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNIT 2 - ISSUANCE OF EXIGENT AMENDMENT RE: EXTEND IMPLEMENTATION PERIOD FOR AMENDMENT NO. 174- LEAK DETECTION SYSTEM SETPOINT AND ALLOWABLE VALUE CHANGES (TAC NO. MF5695)
Dear Mr. Hanson:
The Commission has issued the enclosed Amendment No. 177 to Renewed Facility Operating License No. NPF-85 for Limerick Generating Station (LGS), Unit 2. This amendment is in response to your application dated February 12, 2015.
The amendment extends the implementation period for Amendment No. 174, "Leak Detection System Setpoint and Allowable Value Changes," which was issued on December 29, 2014.
Amendment No. 174 was effective as of the date of issuance (i.e., on December 29, 2014) and was required to be implemented within 60 days (i.e., by February 27, 2015). As discussed in your application, the implementation period of 60 days in Amendment No. 174 could not be met due to unforeseen difficulties associated with calibration of a temperature indicating switch.
Amendment No. 177 extends the implementation period for Amendment No. 174 from 60 days to prior to startup from the spring 2015 refueling outage.
A copy of our safety evaluation (SE) is also enclosed. The SE describes the exigent circumstances under which the amendment was issued and provides a final no significant hazards consideration determination. The Notice of Issuance, addressing the final no significant hazards determination and opportunity for a hearing, will be included in the Commission's biweekly Federal Register notice.
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-353
Enclosures:
- 1. Amendment No. 177 to Renewed NPF-85
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED ST ATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 Renewed License No. NPF-85
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee), dated February 12, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, Renewed Facility Operating License No. NPF-85 is amended to extend the implementation date of Amendment No. 174, issued on December 29, 2014, to prior to startup from the Spring 2015 Unit 2 Refueling Outage.
- 3. This license amendment is effective as of its date of issuance and shall be implemented prior to startup from the Spring 2015 Unit 2 Refueling Outage.
FOR THE NUCLEAR REGULATORY COMMISSION Douglas A. Broaddus, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: February 25, 2015
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 177 TO RENEWED FACILITY OPERATING LICENSE NO NPF-85 EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNIT 2 DOCKET NO. 50-353
1.0 INTRODUCTION
By application dated February 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15043A649), Exelon Generation Company, LLC (Exelon, the licensee), submitted an amendment request for Limerick Generating Station (LGS), Unit 2.
The proposed amendment would extend the implementation period for Amendment No. 174, which was issued by the Nuclear Regulatory Commission (NRG or the Commission) staff on December 29, 2014 (ADAMS Accession No. ML14324A808). Amendment No. 174 was effective as of the date of issuance (i.e., on December 29, 2014) and was required to be implemented within 60 days (i.e., by February 27, 2015). Due to unforeseen difficulties associated with calibration of a temperature indicating switch, Exelon requested that the implementation period be extended. Specifically, Exelon requested that implementation not be required until prior to startup from the spring 2015 refueling outage for LGS, Unit 2.
Amendment No. 174 revised technical specification (TS) setpoints and allowable values for certain area temperature instrumentation associated with the leak detection system (LOS). The purpose of the LOS is to detect and provide the signals necessary to isolate leakage from the reactor coolant pressure boundary before pre-determined limits are exceeded. The affected TS instrumentation monitor ambient temperature in the reactor water cleanup system area, the high pressure coolant injection equipment room and pipe routing area, and the reactor core isolation cooling equipment room and pipe routing area. The changes made by Amendment No. 174 established new temperature setpoint values such that normal variations in the maximum operating temperatures for the affected plant areas would not result in spurious system isolations.
As discussed in the licensee's application dated February 12, 2015, Exelon requested that the proposed amendment be processed by the NRG on an exigent basis in accordance with the provisions in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.91 (a)(6). The NRC's evaluation regarding the exigent circumstances is discussed below in Safety Evaluation (SE) Section 4.0.
Enclosure 2
2.0 REGULATORY EVALUATION
In issuing an amendment to an operating license, the NRC staff specifies when the amendment is effective and when the amendment must be implemented. Enclosure 2 to the NRC's letter dated December 29, 2014, contained Amendment No. 174 for LGS, Unit 2. The amendment stated, in part, that:
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
There are no specific regulatory requirements regarding the time period for amendment implementation. The NRC staff generally specifies an implementation period consistent with that requested in the licensee's application. For LGS, Unit 2, Amendment No. 174, the 60-day period was requested in Exelon's letter dated December 6, 2013 (ADAMS Accession No. ML13343A024).
Implementation periods, requested by licensees, may vary based on the extent of the physical changes needed to the plant and/or associated documentation that needs to be revised.
Sometimes the licensee requests that it be allowed to implement the amendment during the next refueling outage to support changes that the licensee wants to make when the plant is shutdown.
Since the implementation period specified by the NRC in an amendment is considered part of the operating license, the licensee is required to fully implement the amendment by the date specified (i.e., by a date no later than that specified) or be in violation of its operating license.
Any extension of the implementation period needs prior NRC approval as a license amendment pursuant to 10 CFR 50.90.
3.0 TECHNICAL EVALUATION
As discussed in SE Section 1.0, LGS, Unit 2 Amendment No. 174 was effective as of the date of issuance (i.e., on December 29, 2014) and was required to be implemented within 60 days (i.e., by February 27, 2015). Due to unforeseen difficulties associated with calibration of a temperature indicating switch, Exelon requested that the implementation period be extended.
Specifically, Exelon requested that implementation not be required until prior to startup from the spring 2015 refueling outage for LGS, Unit 2.
The problem, associated with the calibration of the temperature indicating switch, involved an inoperable key pad needed to make the associated setpoint changes approved in Amendment No. 174. The changes made by Amendment No. 174 established new temperature setpoint values such that normal variations in the maximum operating temperatures for the affected plant areas would not result in spurious system isolations. The inability to revise the setpoints, due to the inoperable key pad, does not affect the ability of the temperature indicating switch to perform its design basis intended functions with the currently calibrated setpoints.
The NRC staff finds that the proposed extension of the implementation period for LGS, Unit 2 Amendment No. 174 is purely administrative in nature. The proposed amendment does not involve any physical changes to the plant and does not involve any changes in the operation of
the plant. Operation of the plant with the currently calibrated setpoints (i.e., setpoints prior to approval of Amendment No. 174) does not raise any safety concerns. Based on the above considerations, the NRC staff concludes that the proposed amendment is acceptable.
4.0 EXIGENT CIRCUMSTANCES
4.1 Background The NRC's regulations contain provisions for issuance of amendments when the usual 30-day public comment period cannot be met. These provisions are applicable under exigent circumstances. Consistent with the requirements in 10 CFR 50.91(a)(6), exigent circumstances exist when: (1) a licensee and the NRC must act quickly; (2) time does not permit the NRC to publish a Federal Register notice allowing 30 days for prior public comment; and (3) the NRC determines that the amendment involves no significant hazards consideration. As discussed in the licensee's application dated February 12, 2015, the licensee requested that the proposed amendment be processed by the NRC on an exigent basis.
Under the provisions in 10 CFR 50.91 (a)(6), the NRC notifies the public in one of two ways:
(1) by issuing a Federal Register notice providing an opportunity for hearing and allowing at least 2 weeks from the date of the notice for prior public comments; or (2) by using local media to provide reasonable notice to the public in the area surrounding the licensee's facility. In this case, the NRC used the second approach and published a public notice in a newspaper local to LGS, The Pottstown Mercury, on February 15 and February 16, 2015.
4.2 Licensee's Basis for Exigent Circumstances The licensee is basing exigent circumstances on the following considerations. During implementation of the various setpoint changes associated with Amendment No. 174 for LGS, Unit 2, an unforeseen equipment problem was identified on February 1, 2015. The problem involved an inoperable key pad needed to make the setpoint changes to one temperature indicating switch. To repair the key pad, equipment would need to be deenergized and removed from service. This would result in declaring equipment inoperable, in accordance with the plant TSs. Based on probabilistic risk assessment and operational risk considerations, the plant would be considered in a higher risk configuration under these circumstances. The extension of the implementation period would allow Exelon to complete the necessary calibration to the temperature indicating switch during less risk-significant operating conditions (i.e., while the plant was shutdown during a refueling outage). Without the proposed amendment, the licensee would be in violation of the LGS, Unit 2 operating license if the changes approved in Amendment No. 174 were not implemented by February 27, 2015.
4.3 NRC Staff Conclusion
Based on the above circumstances, the NRC staff finds that the licensee made a timely application for the proposed amendment following identification of the issue. In addition, the NRC staff finds that the licensee could not avoid the exigency with violating the operating license or by putting the plant in a higher risk configuration. Based on these findings, and the determination that the amendment involves no significant hazards consideration, as discussed
in SE Section 6.0, the NRC staff has determined that a valid need exists for issuance of the license amendment using the exigent provisions of 10 CFR 50.91(a)(6).
5.0 PUBLIC COMMENTS As discussed in SE Section 4.1, the NRC staff published a public notice concerning the proposed amendment, in a newspaper local to LGS, The Pottstown Mercury, on February 15 and February 16, 2015. The notice included the NRC staff's proposed no significant hazards consideration determination. The notice also provided an opportunity for public comment until 5:00 pm on February 24, 2015, regarding the staffs proposed no significant hazards consideration determination.
Public comments were received regarding the proposed amendment. Specifically, the Alliance for a Clean Environment (ACE) provided comments in an e-mail dated February 23, 2015 (ADAMS Accession No. ML15054A308).
Consistent with the requirements in 10 CFR 50.91 (a)(2)(ii), and as noted above, the NRC staff's public notice solicited comments specifically on the proposed no significant hazards consideration determination. ACE provided comments regarding its objections to NRC's issuance of the proposed amendment. ACE also provided comments pertaining to LGS that were not related to the proposed amendment. Although none of the ACE comments pertained specifically to the NRC staff's proposed no significant hazards consideration determination, the staff has provided responses below to comments that pertain specifically to the proposed amendment.
With regard to the comments that do not pertain to the proposed amendment, the NRC staff notes that to the extent that ACE believes that LGS is operating unsafely, it can request that the Commission institute a proceeding pursuant to 10 CFR 2.206(a) to modify, suspend, or revoke a license, or for any other action as may be proper.
5.1 Public Comment No. 1 ACE provided the following comment:
We are opposed to NRC staff's proposal to amend Limerick's Unit 2 operating license yet again. Amendment No. 174 was just issued on December 29, 2014, only two months after NRC relicensed Limerick.
NRG Response:
The fact that the LGS, Units 1 and 2, licenses were recently renewed has no bearing on whether the licensee requests or the NRC issues an amendment to those licenses. License renewal pursuant to NRC regulations at 10 CFR Part 54 is distinct from the license amendment process pursuant to 10 CFR Part 50. Each licensing action is reviewed by the NRC staff to ensure that there is reasonable assurance the relevant regulatory requirements will be met and that the proposed change is safe.
5.2 Public Comment No. 2 ACE provided the following comment:
It is incomprehensible that Exelon can't comply with the amendment it requested just two months ago. More disturbing is the fact that NRC states that this new amendment request is "due to unforseen difficulties associated with calibration of a temperature indicating switch" and newly identified problems with an inoperable key pad.
NRG Response:
Amendment No. 174 was issued by the NRC staff about 2 months ago (not requested by Exelon 2 months ago). The licensee explained the circumstances concerning the exigent need for this amendment as described in SE Section 4.2. The NRC staff has determined that a valid need exists for issuance of the license amendment using the exigent provisions of 10 CFR 50.91(a)(6) as described in SE Section 4.3.
5.3 Public Comment No. 3 ACE provided the following comment:
This equipment is essential to the implementation of new [setpoints] and thermal calibrations and is required to be implemented within 60 days of the issuance of Amendment No. 174. (February 27, 2015).
NRC should not allow an amendment to Amendment No. 174 just because Exelon cannot or will not comply with it. Exelon's new amendment request acknowledges inoperable equipment. Inoperable equipment is the reason Amendment No.174 mandates shutdown of Unit 2 as of February 27, 2015 or be in violation of its LGS Unit 2 operating license unless it shuts down.
NRG Response:
As discussed in SE Section 3.0, the NRC staff finds that the proposed extension of the implementation period for LGS, Unit 2 Amendment No. 174 is purely administrative in nature.
The proposed amendment does not involve any physical changes to the plant and does not involve any changes in the operation of the plant.
The inability to revise the setpoints, due to the inoperable key pad, does not affect the ability of the temperature indicating switch to perform its design basis intended functions with the currently calibrated setpoints. Operation of the plant with the currently calibrated setpoints (i.e., setpoints prior to approval of Amendment No. 174) does not raise any safety concerns.
Also, inoperability of the key pad does not impact the operability of the temperature indicating switch. The temperature indicating switch is still operable in accordance with the technical specifications. As such, there is no technical specification requirement for a plant shutdown due to inoperability of the key pad.
6.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
DETERMINATION The NRC's regulations in 10 CFR 50.92 state that the NRC may make a final determination that a license amendment involves no significant hazards consideration if operation of the facility, in accordance with the amendment, would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
As required by 10 CFR 50.91(a), the licensee, in its application dated February 12, 2015, provided its analysis of the issue of no significant hazards consideration, using the standards in 10 CFR 50.92. The NRC staff's evaluation of the issue of no significant hazards consideration is presented below.
First Standard Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment extends the implementation period specified in LGS, Unit 2 Amendment No.174 from 60 days to prior to startup from the spring 2015 Unit 2 refueling outage. As such, the proposed amendment is purely administrative in nature. No physical changes to the plant will occur as a result of the proposed amendment. In addition, the proposed amendment will not change the operation of any plant structure, system, or component (SSC). Therefore, the proposed amendment does not have any effect on the ability of any SSC from performing its intended design function and does not have any impact on the ability of any SSC from preventing or mitigating any previously evaluated accident.
Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Second Standard Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment is purely administrative in nature. The proposed amendment does not involve any physical changes to the plant and does not involve any changes in the operation of the plant. Therefore, the proposed amendment would not introduce any new accident initiators, nor would it have any effect on the capability of any plant SSC to perform its intended safety function.
Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Third Standard Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
Margin of safety is related to the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment) to limit the level of radiation dose to the public. The proposed amendment is purely administrative in nature. The proposed amendment does not involve any physical changes to the plant and does not involve any changes in the operation of the plant. Therefore, the proposed amendment does not have any effect on the capability of the fission product barriers to limit the level of radiation dose to the public.
Therefore, the proposed amendment does not involve a significant reduction in a margin of safety.
Conclusion Based on the above evaluation, the NRC staff concludes that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff has made a final determination that no significant hazards consideration is involved for the proposed amendment and that the amendment should be issued as allowed by the criteria contained in 10 CFR 50.91.
7.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
8.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has made a final determination that no significant hazards consideration is involved for the proposed amendment as discussed above in SE Section 6.0. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
9.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the
amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: R. Ennis Date: February 25, 2015
ML15049A084 *via e-mail OFFICE LPL 1-2/PM LPL 1-2/LA* OGC* LPL1-2/BC LPL1-2/PM NAME REnnis A Baxter YLindell DBroaddus REnnis DATE 02/24/15 02/24/15 02/24/15 02/25/15 02/25/15