Letter Sequence Approval |
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EPID:L-2018-LLR-0089, Relief Request I4R-18 Associated with Inaccessible Emergency Service Water and Residual Heat Removal Service Water Pump Supports (Approved, Closed) |
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MONTHYEARML19004A3742019-01-0404 January 2019 Relief Request I4R-18 Associated with Inaccessible Emergency Service Water and Residual Heat Removal Service Water Pump Supports Project stage: Request ML19099A3072019-04-16016 April 2019 Issuance of Relief Request 14R-18 Associated with Inaccessible Supports for the Fourth 10-Year Inservice Inspection Interval Pipping Project stage: Approval 2019-01-04
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Category:Code Relief or Alternative
MONTHYEARML23354A0032024-01-19019 January 2024 Authorization and Safety Evaluation for Alternative Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting 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 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 ML20252A1352020-09-0404 September 2020 Relief Request I4R-24 Associated with Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML20093M8202020-04-0303 April 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLR-0014 (COVID-19)) ML20090A6522020-03-31031 March 2020 Verbal Authorization of Relief Request GVRR-9 ML20089A0072020-03-31031 March 2020 Verbal Authorization by the Office of Nuclear Reactor Regulation for Relief Request I4R-23 ML20089A0082020-03-29029 March 2020 Relief Request GVRR-9 Associated with Pandemic Related Issues - Inservice Testing Interval Extension for Motor Operated Valves ML20088B0222020-03-28028 March 2020 Relief Request I4R-23 Associated with Pandemic Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML19228A1952019-10-28028 October 2019 Safety Evaluation of Relief Requests GVRR-8, 11-PRR-1 and 47-VRR-2 Fourth 10-Year Interval of the Inservice Inspection Program EPID L-2018-LLR-0384, EPID L-2018-LLR-0385, EPID L-2018-LLR-0386, and ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 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 ML19009A0022019-03-0505 March 2019 Issuance of Relief Request IR4-17, Revision 1, Reactor Pressure Vessel Nozzle Repair in Lieu of Specific ASME Code Requirements JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds ML18274A0152018-10-0101 October 2018 Relief Request 14R-OB, Revision 1, Associated with Pressure Testing of Containment Atmospheric Control Penetration Piping ML18165A0022018-06-11011 June 2018 Relief Request 14R-18 Associated with Inaccessible Emergency Service Water and Residual Heat Removal Service Water Pump Supports JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML18129A3312018-05-0404 May 2018 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs ML17208A0902017-08-14014 August 2017 Relief Request I4R-17 Associated with the Alternate Repair of a 2-Inch Instrument Line Nozzle at Penetration N-16D on the Reactor Pressure Vessel ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17137A3072017-05-17017 May 2017 Verbal Authorization by the Office of Nuclear Reactor Regulation for Relief Request I4R-17 ML17004A0632017-02-0707 February 2017 Proposed Alternative Request GVRR-8 Inservice Testing Program Third 10-Year Interval ML16344A3242016-12-29029 December 2016 Safety Evaluation of Relief Request I4R-01 for the Fourth 10-Year Interval of the Inservice Inspection Program for Limerick Generating Station, Units 1 and 2 ML16301A4012016-11-21021 November 2016 Safety Evaluation of Relief Requests I4R-02 and I4R-10 for the Fourth 10-Year Interval of the Inservice Inspection Program for Limerick Generating Station, Units 1 and 2 ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0930803822009-11-17017 November 2009 Evaluation of Relief Requests Associated with the Third Inservice Testing Interval (TAC ME0742 - ME0751) ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0312601152003-06-23023 June 2003 Relief Request Review, American Society of Mechanical Engineers Boiler and Pressure Vessel Code-Relief for Qualification Requirements for Dissimilar Metal Piping Welds ML0311300292003-05-0505 May 2003 Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Concerning Check Valve Inservice Testing Program, MB4804 & MB4805 ML0306204912003-03-0303 March 2003 Relief, American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Relief for Risk-Informed Inservice Inspection of Piping, MB4633 and MB4634 ML0208701612002-05-0202 May 2002 Evaluation of Relief Requests RR-05, RR-07, RR-12, Tables RR-12-5 and RR-12-9 and RR-13, Tables RR-13-8 (TAC Nos. MB1018 and MB1019) ML0210607752002-05-0202 May 2002 Evaluation of Relief Request RR-12, Table RR-12-6, Rotation of Snubbers and Relief Valves (TAC Nos. MB1018 and MB1019) ML0208604792002-03-15015 March 2002 Request for Relief, Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Class 1 & 2 Piping ML0201501402002-02-14014 February 2002 Evaluation of Relief Request RR-12, Table RR-12-7, Underwater Welding (Tac Nos. MB1018 and MB1019) ML0202502652002-02-14014 February 2002 Evaluation of Relief Request RR-04 - ASME Class 1, 2, 3 Snubbers Visual Examination and Functional Testing (TAC Nos. MB1018 and MB1019) 2024-01-19
[Table view] Category:Letter
MONTHYEARIR 05000352/20243012024-02-0202 February 2024 Initial Operator Licensing Examination Report 05000352/2024301 and 05000353/2024301 IR 05000352/20230042024-01-31031 January 2024 Integrated Inspection Report 05000352/2023004 and 05000353/2023004 IR 05000352/20240112024-01-31031 January 2024 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000352/2024011 ML24026A2962024-01-26026 January 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)- Syrs, . ML24004A0342024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0026 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000352/20230102024-01-11011 January 2024 Age-Related Degradation Report 05000352/2023010 and 05000353/2023010 IR 05000352/20234012023-12-21021 December 2023 Cybersecurity Inspection Report 05000352/2023401 and 05000353/2023401 ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23333A2182023-11-29029 November 2023 Operator Licensing Examination Approval ML23325A2062023-11-21021 November 2023 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 ML23313A0432023-11-13013 November 2023 Summary of Regulatory Audit in Support of Amendment Request for Control Room Air Conditioning Technical Specifications ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000352/20230032023-10-27027 October 2023 Integrated Inspection Report 05000352/2023003 and 05000353/2023003 and Independent Spent Fuel Storage Installation Inspection 07200065/2023001 ML23297A1722023-10-24024 October 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000352/2024010 and 05000353/2024010 IR 05000352/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000352/2023501 and 05000353/2023501 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23276A5162023-10-0303 October 2023 Federal Emergency Management Agency Level 1 Finding from 2023 Evaluated Emergency Preparedness Exercise ML23275A1082023-09-29029 September 2023 FEMA Level 1 Findings Limerick NPP- Boyertown/Colebrookdale ML23241A9452023-09-27027 September 2023 Generation Station, Units 1 and 2 Regulatory Audit Plan Supporting Review of the Equipment Qualification Portion of Limerick Digital Instrumentation and Controls License Amendment Request ML23269A0522023-09-26026 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000352/2023010 and 05000353/2023010 ML23255A0952023-09-12012 September 2023 Resubmittal of 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) to Address ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23249A1002023-09-0606 September 2023 Requalification Program Inspection IR 05000352/20230052023-08-31031 August 2023 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2023005 and 05000353/2023005) ML23248A2082023-08-31031 August 2023 UFSAR Cover Page ML23242A2172023-08-30030 August 2023 Response to Request for Additional Information for Application to Adopt TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems and Associated Technical Specification Changes NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23228A0942023-08-16016 August 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . IR 05000352/20230022023-08-14014 August 2023 Integrated Inspection Report 05000352/2023002 and 05000353/2023002 ML23220A0182023-08-0808 August 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000352/2023401 and 05000353/2023401 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212B2362023-07-31031 July 2023 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 - WEC Documents ML23212B1052023-07-31031 July 2023 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 - Revise ML23202A2192023-07-21021 July 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . ML23193B0122023-07-20020 July 2023 Audit Plan in Support of Review of License Amendment Request and Exemption Request for Digital Instrumentation and Controls Installation Support (Epids L-2023-LLA-0025 and L-2023-LLE-0005) ML23187A0962023-07-19019 July 2023 Generation Station, Unit Nos. 1 and 2 - Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23208A1522023-07-0606 July 2023 PEMA Letter Dated 7-6-23 Re Limerick Exercise 9-26-23 ML23177A2242023-06-26026 June 2023 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 . ML23145A1972023-06-23023 June 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 255, 256, 257, 258, 259, and 260 2024-02-02
[Table view] Category:Safety Evaluation
MONTHYEARML23321A2362023-12-14014 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 ML19009A0022019-03-0505 March 2019 Issuance of Relief Request IR4-17, Revision 1, Reactor Pressure Vessel Nozzle Repair in Lieu of Specific ASME Code Requirements 2023-05-17
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 16, 2019 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - ISSUANCE OF RELIEF REQUEST 14R-18 ASSOCIATED WITH INACCESSIBLE SUPPORTS FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PIPING (EPID L-2018-LLR-089)
Dear Mr. Hanson:
By letter dated June 11, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18165A002) as supplemented by letter dated January 4, 2019 (ADAMS Accession No. ML19004A374), Exelon Generation Company, LLC (Exelon, the licensee) requested an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code),Section XI, for visual examinations of emergency service water and residual heat removal service water pump supports at the Limerick Generating Station (Limerick), Units 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2),
Exelon requested authorization to use the proposed alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the proposed alternative 14R-18 provides reasonable assurance of the structural integrity of the emergency service water and residual heat removal service water pump upper and lower seismic supports, and that complying with the specified ASME Code requirement would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2), and therefore, authorizes the use of proposed alternative 14R-18 at the Limerick, Units 1 and 2, for the fourth 10-year inservice inspection interval, which commenced on February 1, 2017, and is scheduled to end on January 31, 2027.
B. Hanson All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
If you have any questions, please contact the Limerick Project Manager, V. Sreenivas, at 301-415-2597 or V.Sreenivas@nrc.gov.
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 14R-18 ASSOCIATED WITH INACCESSIBLE SUPPORTS FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL EXELON GENERATION LIMERICK GENERATNG STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353
1.0 INTRODUCTION
By letter dated June 11, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18165A002) as supplemented by letter dated January 4, 2019 (ADAMS Accession No. ML19004A374), Exelon Generation Company, LLC (Exelon, the licensee), requested an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code),Section XI, for visual examinations of emergency service water (ESW) and residual heat removal service water (RHRSW) pump supports at Limerick Generating Station (Limerick), Units 1 and 2.
Specifically, pursuant to Title 1O of the Code of Federal Regulations (10 CFR) 50.55a(z)(2),
Exelon proposes to perform a best effort VT-3 visual examination of the upper seismic support each time the ESW or RHRSW pump is disassembled and removed for maintenance, in lieu of the 100 percent VT-3 examination of the ESW and RHRSW pump supports. The licensee requested authorization to use the proposed alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
2.0 REGULATORY REQUIREMENTS The regulations in 10 CFR 50.55a(g)(4) require that ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(a), 12 months prior to the start of the 120-month interval, subject to the conditions listed therein.
Enclosure
The regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements of 10 CFR 50.55a(g) may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC), if (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety Based on the above, and subject to the following technical evaluation, the NRC staff concludes that regulatory authority to authorize an alternative to the ASME Code requirement, as requested by the licensee exists. Accordingly, the NRC staff has reviewed and evaluated the licensee's request pursuant to 10 CFR 50.55a(z)(2).
3.0 TECHNICAL EVALUATION
3.1 Licensee's Relief Request ASME Code Components Affected (As stated)
Code Class 3 Examination Category: F-A Item Number: F1 .40, Supports Other Than Pipe Supports Component Numbers:
ESW Pump Upper Support Lower Support A OA-P548-SRUP OA-P548-SRLO B OB-P548-SRUP OB-P548-SRLO C OC-P548-SRUP OC-P548-SRLO D OD-P548-SRUP OD-P548-SRLO RHRSW Pump Uooer Support Lower Support A QA- P506-SRUP OA- P506-SRLO B OB- P506-SRUP OB- P506-SRLO C QC- P506-SRUP QC- P506-SRLO D OD- P506-SRUP OD- P506-SRLO Applicable Code Requirements (As stated)
The Code of Record for Limerick's fourth inservice inspection interval, which began February 1, 2017, is the ASME Code,Section XI, 2007 Edition with the 2008 Addenda.
ASME Code,Section XI, IWF-2500, Table IWF-2500-1, Code Category F-A, Item Number F1 .40, Supports Other Than Pipe Supports, requires a VT-3 examination of 100 percent of the Class 3 component supports, as modified by Note 3. Note 3 states that "for multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined."
A VT-3 examination is conducted to determine the general mechanical and structural condition of components and their supports in accordance with IWA-2213. The VT-3 procedure shall be demonstrated capable of resolving characters as specified in Table IWA-2211-1. Remote visual examinations may be utilized, provided the procedure is demonstrated capable of resolving characters in accordance with Table IWA-2211-1.
Reason for Request (As stated)
Pursuant to 10 CFR 50.55a(z)(2), relief is requested from the ASME Code-required 100 percent VT-3 examination of the ESW and RHRSW pump supports, on the basis that compliance with these specified ASME Code requirements is a hardship, without a compensating increase in the level of quality and safety. Limerick, Units 1 and 2, have common ESW and RHRSW systems.
The ESW system provides cooling water flow to essential equipment during a loss-of-offsite power or loss-of-coolant accident, as described in the Limerick, Units 1 and 2, Updated Final Safety Analysis Report (UFSAR), Section 9.2.2, "Emergency Service Water System." The RHRSW system provides a reliable source of cooling water for all operating modes of the residual heat removal (RHR) system, including heat removal under post-accident conditions. It also provides water to flood the reactor core or to spray the primary containment after an accident, if necessary, as described in the UFSAR, Section 9.2.3, "RHR Service Water System."
There are two carbon steel seismic restraints (i.e., the upper support and lower support) around the column of each ESW and RHRSW pump. These restraints limit the movement of the pump columns during a seismic event. At the nominal spray pond water level (elevation 251'), the upper seismic restraint is partially covered by raw water (i.e., spray pond inventory), and the lower seismic restraint is fully submerged. The design of the spray pond pump structure does not allow the inspection of the seismic restraints to be performed unless the pumps are removed from the pump pit.
In the last 7 years, six of the eight (three ESW and three RHRSW) pumps have been replaced.
With the old pump removed, a VT-3 examination of the upper and lower supports was attempted. Due to poor water clarity, a remote inspection was attempted at approximately 6" from the support; however, the ASME Code-required visual prerequisites could not be obtained.
Additionally, there was scaling on the seismic restraint that could not be removed for the inspection. Due to the poor water clarity and the buildup of scale on the supports, a qualified VT-3 examination could not be performed.
Although a qualified VT-3 examination could not be performed, the inspection did assess the condition of the seismic supports to the best of our ability. The attempted examination found no evidence of structural deformation, missing, detached, or loosened items.
Sluice gates can be closed to isolate an ESW/RHRSW wet well from the spray pond, and the ESW/RHRSW pump wet well could potentially be drained. However, when the three sluice gates of an ESW/RHRSW pump wet well are closed, one loop of ESW and one loop of RHRSW are isolated from the spray pond. This alignment would place Limerick, Units 1 and 2, in a 72-hour shutdown action (Technical Specification (TS) 3.7.1.1, Action a.3, for the RHRSW system, and TS 3.7.1.2, Action a.3, for the ESW system).
Limerick, Units 1 and 2, have never used the sluice gates to drain an ESW/RHRSW pump wet well. Based on review of the ESW and RHRSW system out-of-service durations associated with previously completed pump replacement activities, physical work for motor and pump removal, and reinstallation and post-maintenance testing, requires a minimum of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />.
Therefore, the additional activities associated with draining and refilling the pump wet well, scaffold installation/removal, and restraint cleaning/inspection could not be performed within a 72-hour limiting condition for operation, which would result in a dual unit shutdown due to inoperability of one loop of ESW and RHRSW for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
To perform a qualified VT-3 examination of the ESW and RHRSW pump seismic restraints, a modification to the spray pond pumphouse structure would be necessary to isolate each pump compartment by possibly adding sluice gates for each individual RHRSW and ESW pump.
Currently, each compartment contains two ESW pumps and two RHRSW pumps (i.e., one loop of each system). Without such modifications, the actions required to perform a qualified VT-3 examination of the ESW and RHRSW seismic restraints cannot be performed within the 72-hour limiting condition for operation, and therefore, a dual unit outage is required to comply with the ASME Code. Accordingly, performing this inspection is a hardship, without a compensating increase in the level of quality or safety.
Proposed Alternative and Basis for Use (As stated)
As an alternative to performing a qualified VT-3 examination of the ESW and RHRSW seismic restraints, Limerick, Units 1 and 2, will perform a best effort visual examination of the upper seismic restraint each time an ESW or RHRSW pump is disassembled and removed for maintenance. This examination will be performed remotely, to look for evidence of structural deformation and missing, detached, or loosened support items. The upper seismic restraint is located in the most limiting environment, since it is exposed to continuous wet and dry cycles due to normal variations in spray pond water level.
Additionally, from a review of the design calculation, there is a minimum safety factor of 25 based on the operating basis earthquake (QBE) allowable stresses; this margin is available for any material loss due to corrosion. With this available margin, a best-effort visual examination is sufficient to identify degradation that would affect the ability of the ESW and RHRSW seismic restraints to perform their function, and therefore, provides an acceptable alternative to the ASME Code-required VT-3 examination 3.2 NRC STAFF EVALUATION The NRC staff has evaluated the proposed alternative 14R-18 pursuant to 10 CFR 50.55a(z)(2).
The NRC staff focused on whether compliance with the specified requirements of 10 CFR 50.55a(g), or portions thereof, would result in hardship or unusual difficulty, and if there is a compensating increase in the level of quality and safety despite the hardship. The NRC staff also evaluated the licensee's proposed alternative to determine whether it would provide reasonable assurance of structural integrity of the ESW and RHRSW pump supports.
The NRC staff determined that it would result in hardship if the IWF-2500, Table IWF-2500-1 requirement for VT-3 examination of the upper and lower seismic supports of an ESW and RHRSW pump is imposed upon the licensee. This hardship is due to the existing design and configurations of the Limerick, Units 1 and 2, common ESW and RHRSW systems, which would make draining and refilling the pump wet well to allow scaffold installation/removal and restraint cleaning/examination result in a dual unit shutdown, due to inoperability of one loop of ESW and RHRSW for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Without modifications to the spray pond pumphouse structure to isolate each pump compartment by possibly adding sluice gates for each individual RHRSW and ESW pump, the actions required to perform a qualified VT-3 examination of the ESW and RHRSW seismic restraints cannot be performed within the 72-hour limiting condition for operation, and therefore, a dual unit outage would be required to comply with the ASME Code,Section XI.
In evaluating whether the licensee's proposed alternative would provide reasonable assurance of structural integrity of the ESW and RHRSW pump supports, the staff examined the design of
the supports, materials of construction, past operating/maintenance experience, and the proposed future inspection program for the supports in question.
The NRC staffs evaluation of the normal operating and seismic loads provided by the licensee in the January 4, 2019, supplement showed that under normal operation, there is a slight clearance between the pump and the seismic restraint, and therefore, no loads are seen by the restraint. For seismic loading, the maximum loading is considered to be the shear force resulting from the design-basis earthquake. The maximum stresses in the anchor bolts from the seismic event are calculated to be 801 pounds per square inch (psi) for the ESW pumps and 863 psi for the RHRSW pumps. Seismic calculations for the restraints were deemed unnecessary because the design is rigid enough that their participation in the dynamic model is insignificant. The maximum loads expected to be experienced by the restraints is actually hypothesized to be from inadvertently allowing the pump to rest on the supports during handling for maintenance to remove/reinstall the pumps. The maximum stresses in the anchor bolts from the handling event are calculated to be 10,477 psi for the ESW pumps and 13,548 psi for the RHRSW pumps.
The NRC staff evaluated the materials of construction of the restraints provided by the licensee.
The January 4, 2019, supplement identified that the seismic restraints are fabricated from American Society for Testing and Materials (ASTM) A-516 Gr. 70 material and the anchor bolting is ASTM A-193 Gr. B7 bolting material. The allowable stress for the anchor bolts is 25,000 psi. Therefore, the NRC staff finds that the structural integrity of the restraints is reasonably assured for both the seismic and handling event loads because the loads on the anchor bolts are well below the allowable stresses, and the design of the support is such that the restraint thickness and cross-sectional area at all critical locations exceed the total anchor bolt area.
The NRC staff evaluated the past operating and maintenance experience with these supports and the proposed future inspection program. The licensee stated that six of the eight pumps identified in the proposed alternative were replaced in the last 7 years. Best effort examinations were performed on the supports associated with these pumps. The January 4, 2019, supplement stated that there has been no operating or maintenance experience indicative of possible restraint degradation. The proposed alternative would continue to perform a best effort examination of the upper restraint of each pump removed for maintenance rather than limit the examination to one ESW and one RHRSW pump, as allowed by the ASME Code,Section XI.
This examination will be performed remotely to look for evidence of structural deformation and missing, detached, or loosened support items. The upper restraint would logically be expected to experience degradation before the lower support, based on its environment being exposed to continuous wet and dry cycles due to normal variations in spray pond water level. The NRC staff finds that, based on the operating experience with the ESW and RHRSW pump seismic restraints and the licensee's proposed future inspections of the restraints during maintenance of the pumps, structural integrity of the ESW and RHRSW pump seismic restraints is reasonably assured.
In its application, the licensee requested relief for the current fourth 10-year ISi interval and the remainder of plant life for Limerick, Units 1 and 2. The NRC staff finds that the operating experience from the future inspection program proposed in Relief Request 14R-18 may indicate a need to perform additional examinations different from those authorized for the fourth 10-year ISi interval. There may be future technological advances that make it possible to perform the examination of the pump supports remotely, which may eliminate the hardship addressed in Relief Request 14R-18. Further, there may be Code changes that may either tighten or relax
the requirements for the examination of the upper and lower supports for the ESW or RHRSW pumps or changes in future editions of the ASME Code,Section XI.
Based on the above evaluation, the NRC staff finds that the licensee's proposed alternative 14R-18 is only acceptable for the fourth 10-year inservice inspection of Limerick, Units 1 and 2, scheduled to end on January 31, 2027.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the licensee's proposed alternative 14R-18 provides reasonable assurance of the structural integrity of the ESW and RHRSW pump upper and lower seismic supports, and that complying with the specified ASME Code requirement would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(z)(2), and therefore, authorizes the use of proposed alternative 14R-18 at Limerick, Units 1 and 2, for the fourth 10-year inservice inspection interval, which commenced on February 1, 2017, and is scheduled to end on January 31, 2027.
All other ASME Code,Section XI requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including the third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Keith Hoffman Date: April 16, 2019
B. Hanson
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - ISSUANCE OF RELIEF REQUEST 14R-18 ASSOCIATED WITH INACCESSIBLE SUPPORTS FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PIPING (EPID L-2018-LLR-089) DATED APRIL 16, 2019 DISTRIBUTION:
PUBLIC PM File Copy RidsNrrLALRonewicz Resource RidsNrrDorlLpl1 Resource RidsNrrPMLimerick Resource RidsACRS_MailCTR Resource RidsRgn1 MailCenter Resource RidsNrrDmlrMphb Resource SMin, NRR KHoffman, NRR SCumblidge, NRR MMcCoppin, OEDO JQuichocho, OEDO ADAMS A ccess1on No.: ML19099A307 *biy e-ma1*1 **b,y memoran d um OFFICE DORL/LPL 1/PM* DORL/LPL 1/LA DMLR/MPHB/BC** DORL/LPL 1/BC DORL/LPL 1/PM NAME VSreenivas LRonewicz DAIiey JDanna VSreenivas (SCumblidge for) (J Poole for)
DATE 04/11/2019 04/12/2019 02/22/2019 04/12/2019 04/16/2019 OFFICIAL RECORD COPY