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EPID:L-2020-LLR-0046, Relief Request GVRR-9 Associated with Pandemic Related Issues - Inservice Testing Interval Extension for Motor Operated Valves (Approved, Closed) |
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MONTHYEARML20089A0082020-03-29029 March 2020 Relief Request GVRR-9 Associated with Pandemic Related Issues - Inservice Testing Interval Extension for Motor Operated Valves Project stage: Request ML20092L8532020-03-31031 March 2020 Email Limerick Generating Station, Unit 1 (LGS) - MOVs Relief Request Verbal Authorization Related to COVID-19 Issues Project stage: Approval ML20090A6522020-03-31031 March 2020 Verbal Authorization of Relief Request GVRR-9 Project stage: Approval 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)) Project stage: Approval 2020-03-31
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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
MONTHYEARML24303A0902024-10-29029 October 2024 Operator Licensing Examination Approval IR 05000352/20240122024-10-17017 October 2024 Commercial Grade Dedication Inspection Report 05000352/2024012 and 05000353/2024012 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24274A2372024-10-0707 October 2024 – Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications ML24278A3022024-10-0404 October 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A0032024-09-27027 September 2024 Generation Station, Units 1 and 2 – Regulatory Audit Plan Supporting Review of the Component Interface Module System of the Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) (Redacted) ML24243A0482024-09-19019 September 2024 Generation Station, Unit Nos. 1 and 2 - Schedule Update for License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24215A4042024-09-18018 September 2024 Request for Withholding Information from Public Disclosure IR 05000352/20244202024-09-16016 September 2024 – Security Baseline Inspection Report 05000352/2024420 and 05000353/2024420 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds IR 05000352/20250102024-09-10010 September 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000352/2025010 and 05000353/2025010 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000352/20230022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000352/2023002 and 05000353/2023002 IR 05000352/20240052024-08-29029 August 2024 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2024005 and 05000353/2024005) ML24241A1952024-08-28028 August 2024 License Amendment Request for Modification to Technical Specification 3.6.1.2 and Main Steam Isolation Valve Leakage Rate Requirements ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24163A3902024-08-14014 August 2024 Request for Withholding Information from Public Disclosure IR 05000352/20240022024-08-12012 August 2024 Integrated Inspection Report 05000352/2024002 and 05000353/2024002 ML24220A2392024-08-12012 August 2024 Correction to Technical Specification Page 3/4 3-11 in Amendment No. 225 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24204A0712024-07-29029 July 2024 Issuance of Amendment Nos. 263 and 225 Technical Specifications for Main Steam Line Tunnel Temperature ML24208A1592024-07-25025 July 2024 Regulatory Audit Plan Supporting Review of the System Development Portion of Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) - Non-Proprietary ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24201A1662024-07-19019 July 2024 Response to Request for Additional Information for License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam L ML24199A1842024-07-15015 July 2024 RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24180A1572024-06-28028 June 2024 Request to Return and Replace WEC Documents (EQ-EV-386-GLIM, EQ-QR- 433-GLIM, and APP-GW-GLR-611), to Meet 10CFR2.390 Request to Withdraw from Public Disclosure Requirements ML24170A7702024-06-20020 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, Opportunity for Hearing(Epid L-2024-LLA-0079) LTR 05000352/LER-2024-003, Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK1232024-06-18018 June 2024 Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK123 ML24166A1142024-06-14014 June 2024 Response to Requests for Additional Information (RAIs 15 Through 23) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24165A2642024-06-13013 June 2024 License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam Line Tunnel Temperature TS 3/4.7.9 05000352/LER-2024-001, 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 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 ML24151A2012024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24151A2882024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24150A0242024-05-29029 May 2024 Notification of Commercial Grade Dedication Inspection (05000352/2024012 and 05000353/2024012) and Request for Information ML24149A2112024-05-28028 May 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000352/20243022024-05-20020 May 2024 Revised Initial Operator Licensing Examination Report 05000352/2024302 and 05000353/2024302 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000352/20240012024-05-0707 May 2024 Integrated Inspection Report 05000352/2024001 and 05000353/2024001 ML24124A0432024-05-0303 May 2024 Response to Requests for Additional Information (RAIs 9 Through 14) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24114A3222024-04-23023 April 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) - Pivot to Unit ML24109A0702024-04-18018 April 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFRC50.52 ATWS Rule to Support the Digital Modernization Project Installation . ML24093A0912024-04-17017 April 2024 Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24106A1832024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases 2024-09-06
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200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.55a March 29, 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Unit 1 Renewed Facility Operating License No. NPF-39 NRC Docket No. 50-352
Subject:
Relief Request GVRR-9 Associated with Pandemic Related Issues - Inservice Testing Interval Extension for Motor Operated Valves Based on the current situation associated with pandemic related issues, Exelon Generation Company, LLC (Exelon) is requesting a proposed alternative to the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the Inservice Testing Program. Attached is the proposed alternative associated with Inservice Testing Interval extension for certain Limerick Generating Station (LGS), Unit 1, Motor Operated Valves (MOVs).
At the current time, Exelon is reducing activities associated with the LGS, Unit 1, outage which began on Saturday, March 28, 2020, in order to limit the spread of the COVID-19 virus. As discussed in the relief request, many of these activities involve close contact and a limit to social distancing. Further review has determined that close contact required to perform the MOV testing would be detrimental to the occupational health and safety of the workforce and result in the potential to spread the virus. Additionally, the station may experience critical shortages of specially trained and qualified personnel due to illness which will greatly affect completion of these required tests during the current refuel outage.
Accordingly, Exelon is requesting approval of this relief on an expedited basis.
Due to the urgent nature of this situation, Exelon is requesting approval of the attached relief request by March 31, 2020.
There are no regulatory commitments in this letter.
U.S. Nuclear Regulatory Commission Relief Request GVRR-9 Associated with Pandemic Related Issues for MOVs Docket No. 50-352 March 29, 2020 Page 2 If you have any questions concerning this letter, please contact David Neff at (267) 533-1132.
Respectfully, David P. Helker Sr. Manager, Licensing Exelon Generation Company, LLC
Attachment:
Relief Request GVRR-9 Associated with Pandemic Related Issues - lnservice Testing Interval Extension for Motor Operated Valves cc: w/ Attachments Regional Administrator - NRG Region I NRG Senior Resident Inspector - Limerick Generating Station NRG Project Manager - Limerick Generating Station R. R. Janati, Pennsylvania Bureau of Radiation Protection
Attachment Relief Request GVRR-9 Associated with Pandemic Related Issues - Inservice Testing Interval Extension for Motor Operated Valves
EXELON GENERATION COMPANY, LLC IST PROGRAM - RELIEF REQUEST Limerick Generating Station Unit 1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
Associated with Pandemic Related Issues GVRR-9, Revision 0, Inservice Testing Interval Extension for Motor Operated Valves
- 1. ASME Code Component(s) Affected The following 17 active safety related motor operated valves (MOVs) are required by Subsection ISTC of the 2012 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code to be tested in accordance with ASME OM Code Mandatory Appendix Ill.
Component System Code Class Category Type 1 HV-013-106 Reactor Enclosure Cooling Water 2 A MO 2 HV-013-108 Reactor Enclosure Cooling Water 2 A MO 3 HV-013-111 Reactor Enclosure Cooling Water 2 A MO 4 HV-041-130B Nuclear Boiler 1 A MO 5 HV-041-140 Nuclear Boiler NC B MO 6 HV-046-125 Control Rod Drive Hydraulic NC B MO 7 HV-048-1F006B Standby Liquid Control 1 A/C MO 8 HV-051-1F008 Residual Heat Removal 1 A MO 9 HV-051-1F009 Residual Heat Removal 1 A MO 10 HV-057-162 Containment Atmospheric Control 2 A MO 11 HV-057-163 Containment Atmospheric Control 2 A MO 12 HV-059-101 Primary Containment Instrument Gas 2 A MO 13 HV-059-151A Primary Containment Instrument Gas 2 A MO 14 HV-059-151B Primary Containment Instrument Gas 2 A MO 15 HV-087-120A Drywell Chilled Water NC A MO 16 HV-087-121B Drywell Chilled Water NC A MO 17 HV-087-123 Drywell Chilled Water 2 A MO
2. Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2012 Edition with no addenda.
3. Applicable Code Requirement
The ASME OM Code Mandatory Appendix III, Preservice and lnservice testing of Active Electric Motor-Operated Valve Assemblies in Water Cooled Reactor Nuclear Power Plants.
The following Appendix Ill Paragraphs are affected by this Relief Request (RR) for a one-time IST Program interval extension to the next refueling outage for specific Limerick Generating Station (LGS), Unit 1, MOVs.
Page 1 of 5
EXELON GENERATION COMPANY, LLC IST PROGRAM - RELIEF REQUEST Limerick Generating Station Unit 1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
Associated with Pandemic Related Issues GVRR-9, Revision 0, Inservice Testing Interval Extension for Motor Operated Valves III-3310 Inservice Test Interval. (c) The maximum inservice test interval shall not exceed 10 yr. MOV inservice tests conducted per para. III-3400 may be used to satisfy this requirement.
III-3722 LSSC MOVs. (d). LSSC MOVs shall be inservice tested at least every 10 yr in accordance with para. III-3310.
4. Reason for Request
In accordance with 10 CFR 50.55a(z)(2), Exelon Generation Company, LLC (Exelon) is requesting approval for a one-time IST Program interval extension to the next refueling outage for specific LGS, Unit 1, MOVs due to occupational health and safety concerns associated with pandemic related issues. The next refueling outage is currently scheduled for the spring of 2022 (Li1R19). For each of the identified applicable paragraphs, relief is being sought for alternative treatments described in Section 5 of this RR based on the existence of satisfactory MOV performance and capability and that compliance would involve activities that would be detrimental to the occupational health and safety of the workforce and result in the potential to spread the virus. The basis of the request is that compliance results in hardship or unusual difficulty without a compensating increase in level of quality or safety during the current pandemic.
At the current time, Exelon is reducing activities associated with the LGS, Unit 1 outage which began on Saturday, March 28, 2020, in order to limit the spread of the COVID-19 virus. As discussed in this RR, many of these activities involve close contact and a limit to social distancing. Further review has determined that close contact required to perform the MOV testing would be detrimental to the occupational health and safety of the workforce and result in the potential to spread the virus. Additionally, the station may experience critical shortages of specially trained and qualified personnel due to illness which will greatly affect completion of these required tests during the current refueling outage. These tests require several valve maintenance technicians, and other support personnel (e.g., scaffold builders, radiation protection technicians, and other maintenance personnel). Accordingly, Exelon is requesting approval of this relief on an expedited basis.
The United States government declared a national emergency associated with the COVID-19 outbreak on March 13, 2020. In addition, the state of Pennsylvania, where LGS is located, made an Emergency Disaster Declaration on March 5, 2020, to take actions necessary to reduce exposure to the virus associated with the COVID-19 outbreak. The Centers for Disease Control (CDC) is recommending social distancing as it applies to COVID-19. The CDC defines social distancing as "remaining out of congregate settings, avoiding mass gatherings, and maintaining distance (approximately 6 feet or 2 meters) from others when possible." In the case of performing the MOV testing at a nuclear power plant, which requires work in close spaces, this recommendation cannot be effectively implemented.
Due to the COVID-19 pandemic and in an effort to comply with CDC guidance, Exelon is requesting relief associated with performing certain MOV testing. Section 5 of this RR demonstrates that there is reasonable assurance that the design function of each identified Page 2 of 5
EXELON GENERATION COMPANY, LLC IST PROGRAM - RELIEF REQUEST Limerick Generating Station Unit 1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
Associated with Pandemic Related Issues GVRR-9, Revision 0, Inservice Testing Interval Extension for Motor Operated Valves MOV will be maintained through the next refuel outage currently scheduled for the spring of 2022 (Li1R19). The technical justification utilizes available detailed data from the most recent MOV test, the corresponding MOV Functional Margin, and a review of the maintenance history for each MOV. This provides the technical justification necessary to show that the proposed alternative is acceptable, and that deferral of the MOV testing in 2020 will not result in an adverse consequence to safety.
5. Proposed Alternative and Basis for Use
Exelon is requesting relief associated with performing the identified MOV testing in accordance with 10 CFR 50.55a(z)(2) on the basis that compliance results in hardship or unusual difficulty without a compensating increase in level of quality or safety during the current pandemic. Exelon proposes a one-time extension to IST Program intervals for specific LGS, Unit 1, MOVs to the next refueling outage currently scheduled for the spring of 2022 (Li1R19). An evaluation was performed for each identified MOV that utilized detailed data from the most recent MOV test, the corresponding MOV Functional Margin, and a review of the maintenance history for each MOV. This evaluation concluded that the proposed alternative is acceptable, and that deferral of the specific MOV testing in 2020 will not result in an adverse consequence to safety.
Over the past twenty years, Exelon MOV Programs have demonstrated many margin stable MOVs that are being considered for extension of their current MOV Program maximum inservice test intervals of ten years. Exelon submitted a RR for Limerick to permit implementation of the approved Code Case OMN-26 (Reference 1) and the NRC has accepted the requested licensing action (Reference 2). However, the one-time RR contained in this current submittal does not rely on the approval of the Code Case OMN-26 RR.
Table 1 below contains the calculated MOV Functional Margin, after accounting for uncertainties and degradation factors, based on the most current MOV test. An MOVs functional margin is a composite margin that defines the functional capability of the MOV to perform its design basis safety function. Each of these MOVs has a Functional Margin of high (> 10% and < 20%) or very high (> 20%) indicating that there is existing safety margin to assure reliable operation of these MOVs. The evaluation for this RR also included a review of the maintenance history of each MOV. No deficiencies, adverse trends or open maintenance work orders were identified that would impact or degrade each valves performance capability and exclude it from this interval extension RR. Each MOV in the scope of this RR is currently on a standard testing interval with acceptable performance.
Considering the valves current acceptable performance and the high or very high MOV functional margin, there is reasonable assurance that each MOV will continue to be capable of performing its design function during the use of this RR.
In summary, extending the MOV testing interval for each MOV in the scope of this RR to the next refueling outage scheduled for the spring of 2022 (Li1R19) would not adversely impact the function of the MOV or result in a reduction in plant safety. In the current pandemic environment, performing the required tests would result in an increased risk of virus exposure to plant personnel and a reduction in occupational health and safety without a Page 3 of 5
EXELON GENERATION COMPANY, LLC IST PROGRAM - RELIEF REQUEST Limerick Generating Station Unit 1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
Associated with Pandemic Related Issues GVRR-9, Revision 0, Inservice Testing Interval Extension for Motor Operated Valves compensating benefit. Therefore, this RR meets the criteria for relief on the basis that compliance results in hardship or unusual difficulty without a compensating increase in level of quality or safety during the current pandemic.
6. Duration of Proposed Alternative
This submittal requests a one-time IST Program interval extension for specific LGS, Unit 1, MOVs to the next refueling outage that is currently scheduled for the spring of 2022 (Li1R19).
- 7. Precedent None
- 8. References
- 1. Exelon letter to NRC, "Proposed Alternative to Utilize Code Case OMN-26," dated January 31, 2020 (ADAMS Accession No. ML20034C819)
- 2. NRC email to Exelon, "Code Case OMN-26 (EPID L-2020-LLR-0012)," dated February 25, 2020 (ADAMS Accession No. ML20056F345)
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EXELON GENERATION COMPANY, LLC IST PROGRAM - RELIEF REQUEST Limerick Generating Station Unit 1 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
Associated with Pandemic Related Issues GVRR-9, Revision 0, Inservice Testing Interval Extension for Motor Operated Valves Table 1 Comparison of MOV Testing Interval Functional Current MOV ID Last Requested
- Margin Max Number Tested Outage (Year)
Interval 1 HV-013-106 78.5 2010 10 L1R19 (2022) 2 HV-013-108 219.1 2010 10 L1R19 (2022) 3 HV-013-111 226.7 2010 10 L1R19 (2022) 4 HV-041-130B 180.6 2010 10 L1R19 (2022) 5 HV-041-140 74.9 2010 10 L1R19 (2022) 6 HV-046-125 102.3 2010 10 L1R19 (2022) 7 HV-048-1F006B 61.1 2010 10 L1R19 (2022) 8 HV-051-1F008 40.3 2010 10 L1R19 (2022) 9 HV-051-1F009 35.6 2010 10 L1R19 (2022) 10 HV-057-162 98.7 2010 10 L1R19 (2022) 11 HV-057-163 361.0 2010 10 L1R19 (2022) 12 HV-059-101 97.6 2010 10 L1R19 (2022) 13 HV-059-151A 97.1 2010 10 L1R19 (2022) 14 HV-059-151B 283.5 2010 10 L1R19 (2022) 15 HV-087-120A 10.2 2010 10 L1R19 (2022) 16 HV-087-121B 22.7 2010 10 L1R19 (2022) 17 HV-087-123 10.1 2010 10 L1R19 (2022)
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