Letter Sequence Approval |
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EPID:L-2021-LLR-0009, 10 CFR 50.55a Request Number VR-7, Revision 0, Check Valve Testing Extension (Approved, Closed) |
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MONTHYEARL-21-054, 10 CFR 50.55a Request Number VR-7, Revision 0, Check Valve Testing Extension2021-01-29029 January 2021 10 CFR 50.55a Request Number VR-7, Revision 0, Check Valve Testing Extension Project stage: Request ML21054A1782021-02-16016 February 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Acceptance of Relief Request Regarding VR-7 Check Valve Testing Extension Project stage: Acceptance Review ML21050A1072021-02-18018 February 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Request for Additional Information for Proposed Alternative Request VR-7, Rev. 0 Project stage: RAI L-21-080, Response to Requests for Additional Information Re 10 CFR 50.55a Request Numbers VR-3. VR-4. VR-5, VR-61 and VR-7 (EPID Numbers L-2021-LLR-0007, L-2021-LLR-0008, L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)2021-02-22022 February 2021 Response to Requests for Additional Information Re 10 CFR 50.55a Request Numbers VR-3. VR-4. VR-5, VR-61 and VR-7 (EPID Numbers L-2021-LLR-0007, L-2021-LLR-0008, L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011) Project stage: Response to RAI ML21063A1962021-03-0404 March 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Verbal Authorization of Request VR-7, Revision 0 Project stage: Other ML21077A0012021-03-17017 March 2021 NRR E-mail Capture - Perry Nuclear Power Plant - Correction to Acceptance of Relief Requests Regarding VR-3 VR-4, VR-5, VR-6, VR-7, and VR-8 Valve Testing Extensions (Epids: L-2021-LLR-0007 Through L-2021-LLR-0012) Project stage: Acceptance Review ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval Project stage: Approval 2021-02-22
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Similar Documents at Perry |
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Category:Code Relief or Alternative
MONTHYEARML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22136A1132022-06-21021 June 2022 Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097) ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21110A6092021-04-26026 April 2021 Issuance of Relief Requests Vr 3, Revision 0, and Vr 5, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML20363A0062021-01-29029 January 2021 Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval L-21-047, 10 CFR 50.55a Request Numbers VR-3 and VR-5, Valve Testing Extension2021-01-28028 January 2021 10 CFR 50.55a Request Numbers VR-3 and VR-5, Valve Testing Extension ML20311A6582020-11-10010 November 2020 Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval L-20-256, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-28028 September 2020 Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML20266G2652020-09-24024 September 2020 Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20252A0262020-09-18018 September 2020 Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20189A0032020-07-10010 July 2020 Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program L-19-145, 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval2020-01-0606 January 2020 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval ML19029A0902019-02-25025 February 2019 Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096) ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 ML18023A6252018-01-29029 January 2018 Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183) ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17270A0302017-10-16016 October 2017 Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278) ML16328A1252017-01-23023 January 2017 Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (TAC No. MF7780 - MF7783) ML1202501092012-01-31031 January 2012 Safety Evaluation in Support of 10 CFR 50.55A Requests for the Third 10-Year In-Service Inspection Interval JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011 Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP ML1110501052011-04-19019 April 2011 Withdrawal of Requested Licensing Action 10 CFR 50.55A Relief Requests in Support of the Third 10-Year In-Service Inspection Interval, IR-001 and IR-013 ML1032006682010-11-19019 November 2010 Relief Request VR-7, One Time Replacement Frequency Extension ML0928900322009-10-22022 October 2009 Safety Evaluation of Relief Requests for Perry Third 10-Year Pump and Valve Inservice Testing Program ML0926406902009-10-0808 October 2009 Relief Request, PR-3 for Third 10-Year Pump and Valve Inservice Testing Program, TAC ME0820 ML0829607292008-12-29029 December 2008 Request for Relief Related to Inservice Inspection Relief Request IR-054 ML0831002842008-12-16016 December 2008 Request for Relief Related to Inservice Inspection Relief Requests IR-056 and IR-057 L-08-347, Eight Separate In-Service Testing Program 10 CFR 50.55a Alternatives Requests in Support of the Third Ten-Year Interval2008-11-18018 November 2008 Eight Separate In-Service Testing Program 10 CFR 50.55a Alternatives Requests in Support of the Third Ten-Year Interval ML0703607332007-03-0909 March 2007 Request for Relief No. VR-14 Regarding Emergency Service Water Manual Valve Testing Frequency ML0620604472006-07-17017 July 2006 50.55a Request for Alternative Testing Frequency ML0435500732005-01-13013 January 2005 Request to Use Later American Society of Mechanical Engineers Code Edition and Addenda, Request No. IR-053 ML0410400232004-03-31031 March 2004 License Amendment Request Pursuant to 10 CFR 50.90 and Relief Request Pursuant to 10 CFR 50.55a(a)(3) Related to the Testing of Safety/Relief Valves ML0311503132003-05-16016 May 2003 Relief Request for the In-Service Testing Program for Implementation of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Operations and Maintenance Code Case OMN-2 ML0217204622002-06-10010 June 2002 Submittal of In-Service Testing Program Relief Request from Perry Nuclear Power Plant 2022-09-30
[Table view] Category:Letter
MONTHYEARIR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 ML23292A2482023-10-19019 October 2023 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Perry Nuclear Plant, Unit 1, License Renewal, and Concurrence with Not Likely to Adversely Affect Determination for Northern Long-eared Bat ML23292A2472023-10-19019 October 2023 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23249A1032023-10-0303 October 2023 Letter to Rod L. Penfield, Site Vice President-Perry Nuclear Power Plant, Unit 1-Notice of Intent to Conduct Scoping Process and Prepare an Environmental Impact Statement ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23261C3642023-09-25025 September 2023 License Renewal Application Online Reference Portal ML23261B0192023-09-25025 September 2023 Aging Management Audit Plan Regarding the License Renewal Application Review ML23256A3592023-09-22022 September 2023 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Energy Harbor Nuclear Corp. Application for License Renewal L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000440/20234012023-08-28028 August 2023 Public - Perry Nuclear Power Plant Security Baseline Inspection Report 05000440/2023401 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000440/20230052023-08-24024 August 2023 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2023005) ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML23227A2202023-08-15015 August 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Perry Nuclear Power Plant L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications IR 05000440/20230022023-08-0202 August 2023 Integrated Inspection Report 05000440/2023002 L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative ML23198A2842023-07-17017 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant IR 05000440/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection Report 05000440/2023010 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener ML23144A3562023-05-25025 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End of Cycle Plant Performance Assessment of Perry Nuclear Power Plant, Unit 1 L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) IR 05000440/20230012023-05-0404 May 2023 Integrated Inspection Report (05000440/2023001) L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report 2024-01-30
[Table view] Category:Safety Evaluation
MONTHYEARML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22136A1132022-06-21021 June 2022 Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097) ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21063A2532021-03-0505 March 2021 Issuance of Relief Request SR-2, Revision 0, from Certain Requirements of the ASME OM Code (EPID L-2021-LLR-0005 (COVID-19)) ML21063A1572021-03-0404 March 2021 Safety Evaluation for Alternative Request SR-2, Revision 0 Related to one-time Extension Snubbers Testing to ASME OM Code for the Fourth 10-year Inservice Interval at Perry Nuclear Power Plant Unit 1, Docket Nos. 50-440 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20363A0062021-01-29029 January 2021 Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval ML20311A6582020-11-10010 November 2020 Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20266G2652020-09-24024 September 2020 Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20252A0262020-09-18018 September 2020 Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20189A0032020-07-10010 July 2020 Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML19072A0122019-03-15015 March 2019 Correction to License Amendment No. 184 Related to Adoption of Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval ML19029A0902019-02-25025 February 2019 Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096) ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML18023A6252018-01-29029 January 2018 Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183) ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17270A0302017-10-16016 October 2017 Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278) ML17193A3822017-07-18018 July 2017 Correction to Safety Evaluation for License Amendment No. 177 ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) 2023-09-28
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Text
May 4, 2021 Mr. Rod L. Penfield Site Vice President Energy Harbor Nuclear Corp.
Perry Nuclear Power Plant P.O. Box 97, Mail Stop A-PY-A290 Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF RELIEF REQUEST VR-7, REVISION 0, ASSOCIATED WITH THE FOURTH 10-YEAR INSERVICE TESTING INTERVAL (EPID L-2021-LLR-0009 [COVID-19])
Dear Mr. Penfield:
By letter dated January 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21031A002), as supplemented by a , L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)|letter dated February 22, 2021]] (ADAMS Accession No. ML21053A010), Energy Harbor Nuclear Corp. (the licensee) submitted alternative request (AR) No. VR-7, Revision 0, to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to specific requirements in the 2012 Edition of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) at Perry Nuclear Power Plant (PNPP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use the proposed alternative in request VR-7, Revision 0, on the basis that complying with the requirements of the ASME OM Code would result in hardship without a compensating increase in the level of quality and safety.
The NRC staff concludes that request VR-7, Revision 0, will provide reasonable assurance that the check valves at PNPP, listed in the licensees request, are operationally ready to perform their safety functions until the spring 2023 refueling outage. The NRC staff finds that complying with the requirements of the ASME OM Code would result in hardship without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC authorizes the use of request VR-7, Revision 0, at PNPP until the next scheduled refueling outage in spring 2023.
The enclosed safety evaluation documents the technical basis for the NRCs verbal authorization of VR-7, Revision 0, on March 3, 2021 (ADAMS Accession No. ML21063A196).
All other requirements in the ASME OM Code for which relief was not specifically requested and approved in this request remains applicable.
R. Penfield If you have any questions, please contact the Project Manager, Scott Wall, at 301-415-2855 or e-mail at Scott.Wall@nrc.gov.
Sincerely, Digitally signed by Robert F. Robert F. Kuntz Date: 2021.05.04 Kuntz 10:59:24 -04'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST VR-7, REVISION 0 FOURTH 10-YEAR INTERVAL INSERVICE TESTING INTERVAL ENERGY HARBOR NUCLEAR CORP.
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated January 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21031A002), as supplemented by a , L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)|letter dated February 22, 2021]] (ADAMS Accession No. ML21053A010), Energy Harbor Nuclear Corp. (EHNC, the licensee) submitted alternative request (AR) No. VR-7, Revision 0, to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternative to specific requirements in the 2012 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) at Perry Nuclear Power Plant (PNPP) associated with the fourth 10-year interval inservice testing (IST) interval.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee proposed a one-time extension of the testing interval for four specific check valves from the spring 2021 refueling outage (RFO) to the spring 2023 RFO on the basis that complying with the requirements of the ASME OM Code would result in hardship without a compensating increase in the level of quality and safety.
The NRC verbally authorized request VR-7, Revision 0, on March 3, 2021 (ADAMS Accession No. ML21063A196).
2.0 REGULATORY EVALUATION
The NRC regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, state, in part, that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the IST requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and (3) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), to the extent practical within the limitations of design, geometry, and materials of construction of the components.
Enclosure
Regulation 10 CFR 50.55a(z) states, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the NRC, if the licensee demonstrates:
(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.
3.0 TECHNICAL EVALUATION
3.1 Applicable Code Edition and Addenda The licensees OM Code of Record is the 2012 of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a, for the fourth 10-year IST program interval at PNPP, which started on May 18, 2019, and is scheduled to end on May 17, 2029.
3.2 Proposed Alternative VR-7, Revision 0 The IST requirements of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a related to this alternative request, are as follows:
ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, paragraph ISTC-3510, Exercising Test Frequency, states, in part, that:
Active Category A, Category B, and Category C check valves shall be exercised nominally every three months, except as provided by paragraphs ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3570, ISTC-5221, and ISTC-5222.
ASME OM Code, Subsection ISTC-3522, Category C Check Valves, states, in part, that:
If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages.
ASME Code Components Affected In its submittal, the licensee requests a one-time extension of the testing interval for the following four check valves at PNPP:
Table 1 Component ID Component Description Code Valve Class Category Feedwater Header A Outboard 1B21-F032A 1 C Isolation Check Valve Feedwater Header B Outboard 1B21-F032B 1 C Isolation Check Valve Feedwater Header A Containment 1N27-F559A 1 C Check Valve
Feedwater Header B Containment 1N27-F559B 1 C Check Valve 3.3 Reason for Request For VR-7, Revision 0, the licensee requested an alternative to allow a one-time extension of the testing interval for the valves listed in Table 1 of this safety evaluation (SE) at PNPP, during the spring of 2021 RFO. The licensee stated that it will resume the normal outage examination frequency at the next opportunity, currently expected to be the next RFO in spring 2023.
On March 13, 2020, the President of the United States declared a national emergency due to the spread and infectious nature of the Coronavirus-2019 (COVID-19) virus and resulting pandemic. To prevent the spread of COVID-19 and to protect the health and safety of plant personnel while maintaining responsibilities to support critical infrastructure, the licensee intends to reduce the amount of personnel on site, which will pose a hardship for completing the currently planned spring 2021 RFO work scope. With the current work scope and potential loss of personnel, the licensee may not be able to complete the RFO in a timely manner, which could affect critical infrastructure that is needed during this time. The licensee asserted that the testing of the specified check valves at PNPP, during the spring 2021 RFO would result in a hardship without a compensating increase in the level of quality and safety in accordance with 10 CFR 50.55a(z)(2).
3.4 Proposed Alternative The licensee proposed a one-time extension of the exercise testing interval for the check valves listed in its request to the next RFO, scheduled for the spring of 2023. In particular, the licensee proposed to extend the check valve exercise testing interval required by ASME OM Code, Subsection ISTC, paragraphs ISTC-3510 and ISTC-3522(c), until the next RFO, scheduled for the spring of 2023.
The licensee stated that these check valves have a leak rate acceptance criterion of 200 gallons per minute (gpm) when they are tested at 1.1 Pa, where Pa is the limit for the peak containment pressure during a loss of coolant accident. The leakage tests performed on all four of these check valves from 2003 to the present have met the acceptance criterion. The licensee considered that this successful test history supported an extension of the exercise test interval for these check valves.
The licensee asserted that based on the check valves current acceptable performance, there is reasonable assurance that each check valve will be operationally ready to perform its safety function for the duration of this request.
3.5 NRC Staff Evaluation As incorporated by reference in 10 CFR 50.55a, ASME OM Code (2012 Edition),
Subsection ISTC, paragraphs ISTC-3510 and ISTC-3522(c), specify requirements for the exercising of check valves, including the testing intervals. In lieu of performing the check valve exercise testing required by the ASME OM Code during the spring 2021 RFO, the licensee requested a one-time extension of the testing interval for the specified check valves at PNPP to
the next RFO currently scheduled for spring of 2023. In its request, the licensee indicated that these four check valves have met the leak rate acceptance criterion for leakage tests performed from 2003 to the present.
In its , L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)|letter dated February 22, 2021]], the licensee provided a response to a request for additional information from the NRC staff regarding alternative request VR-7. In its response, the licensee indicated the results of the recent leak rate tests conducted to satisfy the exercise close tests for the four check valves. The licensee corrected a reference in its original submittal to the applicable subsection of the ASME OM Code for the subject check valves. The licensee clarified that the four check valves are ASME OM Code Category alternate current valves based on their self-actuating operation and seat leakage limitations.
The NRC staff reviewed the licensees characterization of the hardship posed by the occupational health and safety concerns associated with the pandemic-related issues pertaining to COVID-19. The licensee reported that to prevent the spread of COVID-19 and protect the health and safety of plant personnel, it intended to reduce the amount of personnel on-site during the spring 2021 outage activities. The check valve exercise testing requires specialized external resources such as qualified leak rate contractors to perform the tests and carpenters to erect scaffolding for access to the valves. These external personnel resources could introduce an additional potential to spread the virus, as their medical history could be unknown and exposure to the COVID-19 virus is possible during travel. The NRC staff considers that requiring the check valves listed in the licensees submittal to be exercised during the spring 2021 RFO with limited personnel resources represents a hardship or unusual difficulty without a compensating increase in the level of quality and safety Based on the information described above for the specific check valves at PNPP identified in the licensees submittal, the NRC staff finds that: (1) previous testing of these check valves indicates their acceptable historical performance; (2) no current concerns with the performance of the performance of these check valves have been identified; (3) periodic maintenance activities are not modified by this request; and (4) a hardship exists for the performance of team-oriented exercise testing of these check valves at this time that would be contrary to the health and safety of plant personnel.
Therefore, the NRC staff determined that the licensees proposed alternative for a one-time extension of the exercise testing interval for the four specified check valves at PNPP is acceptable in accordance with 10 CFR 50.55a(z)(2). The proposed alternative will provide reasonable assurance that the check valves listed in the licensees request will be operationally ready to perform their safety functions until the next RFO, scheduled for the spring of 2023.
4.0 CONCLUSION
As set forth above, the NRC staff finds that the proposed alternative described in VR-7, Revision 0, will provide reasonable assurance that the check valves at PNPP, listed in the licensees request are operationally ready to perform their safety functions until the spring 2023 RFO. The NRC staff finds that complying with certain requirements of the ASME OM Code would result in hardship without a compensating increase in the level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC authorizes the use of proposed alternative VR-7, Revision 0, at PNPP, until the next scheduled RFO in the spring of 2023.
All other ASME Code requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable. If the licensee identifies a performance issue with any of these valves, the licensee will be expected to take action to implement the requirements of its technical specifications. This authorization will remain in effect until restart from the next RFO for PNPP, scheduled for the spring of 2023. The licensees testing plans for these check valves may be adjusted as appropriate by any subsequent NRC-authorized alternative requests.
Principal Contributor: N. Hansing T. Scarbrough Date: May 4, 2021
ML21123A289 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EMIB/BC NRR/DORL/LPL3/BC NAME SWall SRohrer ABuford NSalgado (RKuntz for)
DATE 05/04/2021 05/04/2021 04/30/2021 05/04/2021