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 05000440/20240022024-08-0808 August 2024 Integrated Inspection Report 05000440/2024002 L-24-178, License Renewal Application Revision O - Supplement 42024-08-0808 August 2024 License Renewal Application Revision O - Supplement 4 L-24-189, License Renewal Application for Revision O - Supplement 12024-08-0707 August 2024 License Renewal Application for Revision O - Supplement 1 L-24-171, Spent Fuel Storage Cask Registration2024-07-30030 July 2024 Spent Fuel Storage Cask Registration ML24150A2022024-07-25025 July 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-License Renewal Scoping Summary Rpt L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 IR 05000440/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000440/2024401 L-24-036, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-27027 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 IR 05000440/20240112024-06-17017 June 2024 Fire Protection Team Inspection Report 05000440/2024011 ML24157A3782024-06-0606 June 2024 – Revised Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 ML24141A1632024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-116, Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification2024-05-16016 May 2024 Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification L-24-085, Nudear Power Plant, Submittal of Emergency Plan, Revision 622024-05-0606 May 2024 Nudear Power Plant, Submittal of Emergency Plan, Revision 62 L-24-103, Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams2024-05-0202 May 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams ML24117A1222024-04-26026 April 2024 Confirmation of Initial License Examination IR 05000440/20240012024-04-24024 April 2024 Integrated Inspection Report 05000440/2024001 L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report L-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24095A3282024-04-19019 April 2024 License Renewal Revised Schedule Letter L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency2024-04-15015 April 2024 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency L-24-083, Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification2024-04-15015 April 2024 Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification ML24088A1922024-03-28028 March 2024 Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 L-24-057, Submittal of the Decommissioning Funding Status Report2024-03-28028 March 2024 Submittal of the Decommissioning Funding Status Report L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-076, Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-22022 March 2024 Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24064A2212024-03-14014 March 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1 - Summary of the Jan-Feb 2024 Environmental Audit Related to the Review of the License Renewal Application Environmental Report ML24059A3922024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0080 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000440/20230062024-02-28028 February 2024 Annual Assessment Letter for Perry Nuclear Power Plant, Unit 1 (Report 05000440/2023006) L-24-053, Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-02-27027 February 2024 Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 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 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 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 2024-08-08
[Table view] Category:Safety Evaluation
MONTHYEARML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) 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) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments 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 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 ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency 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 ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval 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 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
[Table view] |
Text
July 12, 2022 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 RE: PROPOSED ALTERNATIVE REQUEST VR-12, REVISION 0, ASSOCIATED WITH THE FOURTH 10-YEAR INSERVICE TESTING INTERVAL (EPID L-2022-LLR-0004)
Dear Mr. Penfield:
By letter dated January 5, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22005A351), as supplemented by letter dated April 28, 2022 (ML22118A873), Energy Harbor Nuclear Corp. (the licensee) submitted alternative request No. VR-12, Revision 0, to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to certain inservice testing (IST) program requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) for the Perry Nuclear Power Plant, Unit 1 (PNPP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative in VR-12, Revision 0, on the basis that the proposed alternative will provide an acceptable level of quality and safety.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the proposed alternative in VR-12, Revision 0, for the fourth 10-year IST interval at PNPP which began May 18, 2019, and is scheduled to expire May 17, 2029.
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 Senior Project Manager, Scott Wall, at 301-415-2855 or e-mail at Scott.Wall@nrc.gov.
Sincerely, Digitally signed by Nancy Nancy L. L. Salgado Date: 2022.07.12 Salgado 12:30:08 -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 ALTERNATIVE REQUEST VR-12, 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 5, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22005A351), as supplemented by letter dated April 28, 2022 (ML22118A873), Energy Harbor Nuclear Corp. (the licensee) submitted alternative request for VR-12, Revision 0, to the U.S. Nuclear Regulatory Commission (NRC or Commission) for the use of alternatives to certain inservice testing (IST) program requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) for the Perry Nuclear Power Plant, Unit 1 (PNPP).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative in VR-12, Revision 0, on the basis that the proposed alternative will provide an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
The NRC regulations in 10 CFR 50.55a(f)(4) 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. The IST requirements for pumps and valves that are within the scope of the ASME OM Code but are not classified as ASME Code Class 1, Class 2, or Class 3, may be satisfied as an augmented IST program in accordance with 10 CFR 50.55a(f)(6)(ii) without requesting relief under 10 CFR 50.55a(f)(5) or alternatives under 10 CFR 50.55a(z). This use of an augmented IST program may be acceptable provided the basis for deviations from the ASME OM Code, as incorporated by reference in 10 CFR 50.55a, demonstrates an acceptable level of quality and safety, or that implementing the code provisions would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, where documented and available for NRC review.
Enclosure
The NRC regulations in 10 CFR 50.55a(b)(3)(xi), OM condition: Valve Position Indication, state the following:
When implementing paragraph ISTC-3700, Position Verification Testing, in the ASME OM Code, 2012 Edition through the latest edition and addenda of the ASME OM Code incorporated by reference in paragraph (a)(1)(iv) of this section
[10 CFR 50.55a], licensees shall verify that valve operation is accurately indicated by supplementing valve position indicating lights with other indications, such as flow meters or other suitable instrumentation to provide assurance of proper obturator position for valves with remote position indication within the scope of Subsection ISTC including its mandatory appendices and their verification methods and frequencies.
The regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements in paragraphs (b) through (h) of 10 CFR 50.55a may be authorized by the NRC if the licensee demonstrates that: (1) the proposed alternative provides 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
The information provided by the licensee in support of the requests for alternatives to ASME OM Code requirements has been evaluated and the bases for disposition are documented below.
Applicable Code Edition and Addenda
The 2012 Edition of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a with conditions, is applicable to the current 10-year IST program interval at PNPP.
Duration of the Alternative The duration of the proposed alternatives is for the fourth 10-year ISI interval, which began on May 18, 2019, and is scheduled to end on May 17, 2029.
3.1 Proposed Alternative VR-12, Revision 0 3.1.1 ASME Code Components Affected The request applies to the components in the following table:
Table 1 Valve Number Valve Name System OM ASME Category Code Class 1P87-F046 DRYWELL FLOOR DRN Post Accident Sample A 2 SUMP PEN ISOL VLV System 1P87-F049 RX RECIRC AND RWCU Post Accident Sample A 2 CONT PEN ISOL VLV System 1P87-F052 DRYWELL FLOOR DRN Post Accident Sample A 2 SUMP PEN ISOL VLV System
1P87-055 RX RECIRC AND RWCU Post Accident Sample A 2 CONT PEN ISOL VLV System 1P87-F037 SUP POOL WATER Post Accident Sample A 2 SAMPLE ISOL VLV System 1P87-F083 SUPP POOL RETURN Post Accident Sample A 2 ISOL VLV System 1P87-F0264 SUPP POOL RETURN Post Accident Sample A 2 ISOL VLV System 1D23-F010A SUPR POOL LEVEL A Containment Atmosphere A 2 DRY LEG ISOL VALVE Monitoring 1D23-F010B SUPR POOL LEVEL B Containment Atmosphere A 2 DRY LEG ISOL VALVE Monitoring 1D23-F020A CNTMT PRESS A Containment Atmosphere A 2 CNTMT ISOL VALVE Monitoring 1D23-F020B CNTMT PRESS B Containment Atmosphere A 2 CNTMT ISOL VALVE Monitoring 1D23-F030A CNTMT DW A DIFF Containment Atmosphere A 2 PRESS-CNTMT LEG Monitoring 1D23-F030B CNTMT DW B DIFF Containment Atmosphere A 2 PRESS-CNTMT LEG Monitoring 1D23-F040A CNTMT DW A DIFF Containment Atmosphere A 2 PRESS-DW LEG Monitoring 1D23-F040B CNTMT DW B DIFF Containment Atmosphere A 2 PRESS-DW LEG Monitoring 1D23-F050 SUPR POOL LEVEL C Containment Atmosphere A 2 DRY LEG ISOL VLV Monitoring 1G43-F050A SUPR POOL LEVEL A Suppression Pool Makeup A 2 WET LEG ISOL VALVE 1G43-F050B SUPR POOL LEVEL B Suppression Pool Makeup A 2 WET LEG ISOL VALVE 1G43-F060 SUPR POOL LEVEL C Suppression Pool Makeup A 2 WET LEG ISOL VALVE 1M17-F055 CNTMT VACUUM A Containment Vacuum A 2 CNTMT ISOL VALVE Relief 1M17-F065 CNTMT VACUUM B Containment Vacuum A 2 CNTMT ISOL VALVE Relief Abbreviations Containment CNTMT ll CONT Differential DIFF Drain DRN Drywell DW Isolation ISOL Penetration PEN Pressure PRESS Suppression SUP ll SUPP ll SUPR Reactor RX Reactor Water Cleanup RWCU Recirculation RECIRC Valve VLV
3.1.2 Applicable Code Requirements ASME OM Code, Subsection ISTC, paragraph ISTC-3600, Position Verification Testing, states, in part:
Valves with remote position indicators shall be observed locally at least once every 2 yr [years] to verify that valve operation is accurately indicated. Where practicable, this local observation should be supplemented by other indications such as use of flow meters or other suitable instrumentation to verify obturator position. These observations need not be concurrent. Where local observation is not possible, other indications shall be used for verification of valve operation.
3.1.3 Reason for Request In its submittal dated January 5, 2022, as supplemented by a letter dated April 28, 2022, the licensee provided the following reason for its request:
In accordance with 10 CFR 50.55a, Codes and standards, paragraph (z)(1), an alternative is proposed to ASME OM Code, 2012 Edition, subsection ISTC-3700 for select valves. The basis of the request is that the proposed alternative valve position verification frequencies and leakage tests provide an acceptable level of quality and safety. The current regulation does not allow the test frequency to be altered or adjusted based on existing NRC approved testing, past test performance results, likelihood of failure, nor consequence of failure. The proposed alternative will allow the performance of valve position indication verification and leakage testing to credit existing Code and NRC approved test methodologies and frequencies and be commensurate with the valve's risk ranking.
3.1.4 Licensees Proposed Alternative In its submittal dated January 5, 2022, as supplemented by a letter dated April 28, 2022, the licensee described its proposed alternative as follows:
ISTC-3700 states valves with remote position indicators shall be observed locally at least once every two years to verify that valve operation is accurately indicated. For certain valves at PNPP, 10 CFR 50, Appendix J, Type C testing (specifically, local leak rate testing (LLRT)) is credited to meet the position indication verification requirement. For certain isolation valves on instrument lines that penetrate containment, the inservice testing program utilizes 10 CFR 50, Appendix J, Type C testing methodology to meet the leakage rate and position indication verification requirements. Energy Harbor Nuclear Corp. is proposing to adopt the 10 CFR 50, Appendix J, Option B-Performance-Based Requirements program consistent with [Nuclear Energy Institute] NEI 94-01, Revision 3-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, for PNPP. This program allows LLRT intervals to be extended up to 75 months for valves with a history of satisfactory testing, which entails completion of two consecutive periodic as-found tests where the results of each test are within the allowable administrative limits.
Energy Harbor Nuclear Corp. proposes an alternative to the ASME OM Code, ISTC-3700 requirements, to perform the valve supplemental position verification at a frequency consistent with 10 CFR 50, Appendix J, Type C testing. The NRC approved the use of Option B at PNPP on September 9, 1997 (ML021840313).
The method used at PNPP is a pressure test using LLRT equipment. This method involves pressurizing the containment penetration volume and verifying the penetration remains pressurized while the valve is indicating closed on the main control room board. The valve is then opened using the control switch in the main control room. A decrease in pressure is then verified along with valve position indicating open in the main control room. This method satisfies the requirement for position indication verification and ensures that the indicating system accurately reflects the valve position. The subject valves are all in category A and are all containment isolation valves (CIV) per the plant safety analysis. All the subject valves have a safety function to close to isolate containment during a loss-of-coolant accident (LOCA) when required. Since these valves are CIV, they are individually seat leakage tested in accordance with 10 CFR 50, Appendix J, Option B or the inservice testing program. The subject valves are designed that the position of the valve is not locally observable. The coil position is internal to the valve body and not observable in either the energized or de-energized state.
In the closed direction, the requirements will be met by verifying proper remote indicating lights in conjunction with measured leakage of 1,000 standard cubic centimeters per minute or less for pneumatically tested valves, and 0.5 gallons per minute or less for hydrostatically tested valves using local leak rate testing equipment. These measurements are obtained during execution of test instructions to satisfy the requirements of ASME OM Code-2012, Subsection ISTC-3700, Position Verification Testing.
In the open direction, the requirements will be met by verifying proper remote indicating lights in conjunction with a pressure drop when the valves are opened at test pressure. This is measured immediately following the position verification testing in the closed position described in the preceding paragraph. The test instructions will include acceptance criteria for flow in conjunction with pressure drop to verify accurate indication of obturator position using local leak rate testing equipment. These measurements will be obtained during execution of test instructions to satisfy the requirements of ASME OM Code 2012, Subsection ISTC-3700, Position Verification Testing.
These tests meet the requirements of 10 CFR 50.55a(b)(3)(xi) to verify accurate obturator indication for the valves listed in Table 1 of the letter dated January 5, 2022.
3.1.5 Basis for Use In its January 5, 2022, submittal, the licensee provides a detailed description of the basis for its alternative request. The NRC staff summarizes the licensees description of the basis for use of its alternative request in the following paragraph.
The 10 CFR 50, Appendix J, Type C LLRT intervals may be extended up to 75 months for valves. The NRC has endorsed NEI 94-01, Revision 3-A, as providing an acceptable level of quality and safety. Valves must pass two successful as-found leakage tests to qualify for a 75-month test frequency. A valve demonstrates acceptable performance when it exhibits leakage below the assigned administrative limits. Valves that do not meet the performance standard are tested every refueling interval, in accordance with 10 CFR Part 50, Appendix J, which is more frequent than the most limiting frequency requirement for supplemental position verification of up to two years. The valves in Table 1 have met the performance standard for extension to a 75-month period. A review of the Energy Harbor Nuclear Corporation maintenance and Code-required performance history at PNPP concluded that the valves listed in Table 1 have been reliable. The ASME OM Code, 2012 Edition, requirements for the valves listed in Table 1 have been met, including position indication verification and leakage testing.
This was determined by a review of recorded performance history for the valves in Table 1, which dates back to 2011. All valves were found to have performed satisfactorily. This finding was also supported by a search of condition reports dating back to 2011. There was only one condition report for impaired design, but the valve was later declared satisfactory after evaluation. Therefore, obtaining position verification and leakage testing at a test interval longer than the frequencies specified in ASME OM Code, 2012 Edition, and controlled by 10 CFR Part 50, Appendix J, Option B-Performance-Based Requirements, provides an acceptable level of quality and safety. For the valves listed in Table 1, performing the position verification over an interval consistent with 10 CFR Part 50, Appendix J, aligns with the frequency of an NRC-endorsed testing program. Therefore, the past performance of the valves in Table 1, coupled with the utilization of the robust, performance-based, program requirements from 10 CFR Part 50, Appendix J, Option B, justify that the proposed alternative provides an acceptable level of quality and safety.
3.2 NRC Staff Evaluation The licensee has proposed an alternative test in lieu of the requirements in ASME OM Code, Subsection ISTC, paragraph ISTC-3700, for the valves listed in Table 1 of this SE. Specifically, the licensee proposes to perform the supplemental position verification testing required by 10 CFR 50.55a(b)(3)(xi) in conjunction with the Type C tests (which measure containment isolation valve leakage rates) at a frequency in accordance with the 10 CFR Part 50, Appendix J, Option B, schedule. The applicable valves would initially be tested at the required interval schedule, which is currently every 2 years, as specified by ASME OM Code, Subsection ISTC, paragraph ISTC-3700. Valves that have demonstrated good performance for two consecutive cycles may have their test interval extended to a maximum of 75 months. Any position indication testing failure would require the component to return to the initial interval of every 2 years until good performance can again be established.
To provide reasonable assurance that the testing performed in accordance with Alternative Request VR-12, Revision 0, will meet the requirements of 10 CFR 50.55a(b)(3)(xi), the licensee supplemented Alternative Request VR-12, Revision 0, by a letter dated April 28, 2022, to describe the verification of the valve position indication in both the closed and open directions.
For the closing valve direction, the licensee stated that the requirements will be met by verifying proper remote indicating lights in conjunction with measured leakage of 1,000 standard cubic centimeters per minute or less for pneumatically tested valves, and 0.5 gallons per minute or less for hydrostatically tested valves using local leak rate testing equipment. The licensee reported that these measurements will be obtained during implementation of test instructions to satisfy the requirements of ASME OM Code (2012 Edition), Subsection ISTC, paragraph ISTC-3700, as incorporated by reference in 10 CFR 50.55a.
For the opening valve direction, the licensee stated that the requirements will be met by verifying proper remote indicating lights in conjunction with a pressure drop when the valves are opened at test pressure. The licensee will perform this measurement immediately following the position verification testing in the closed position. The licensees test instructions will include acceptance criteria for flow in conjunction with pressure drop to verify accurate indication of obturator position using local leak rate testing equipment. The licensee will obtain these measurements during implementation of the test instructions to satisfy the requirements of ASME OM Code (2012 Edition), Subsection ISTC, paragraph ISTC-3700, as incorporated by reference in 10 CFR 50.55a.
Based on the information described above for the valves listed in Table 1 of this safety evaluation, the NRC staff finds that (1) previous IST testing including position verification testing for these valves indicates the valves acceptable historical performance; (2) no current concerns with the performance of these valves have been identified; and (3) periodic maintenance activities are not modified by this request. Therefore, the proposed Alternative Request VR-12, Revision 0, provides an acceptable level of quality and safety for the extension of the valve position indication testing interval for the valves listed in Table 1 of this safety evaluation for PNPP.
4.0 CONCLUSION
As set forth above, the NRC staff finds that proposed Alternative Request VR-12, Revision 0, for the valves listed in Table 1 of this safety evaluation will provide an acceptable level of quality and safety for the fourth 10-Year IST Program interval at PNPP, which began on May 18, 2019, and is scheduled to end on May 17, 2029. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for Alternative Request VR-12, Revision 0. Therefore, the NRC authorizes the use of proposed Alternative Request VR-12, Revision 0, for the fourth 10-Year IST Program interval at PNPP.
All other ASME OM Code requirements, as incorporated by reference in 10 CFR 50.55a, for which relief or an alternative was not specifically requested, and granted or authorized (as appropriate), in the subject request remain applicable.
Principal Contributors: Thomas G. Scarbrough, NRR Date: July 12, 2022
ML22187A259
- via memo OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EMIB/BC* NRR/DORL/LPL3/BC SWall SRohrer SBailey NAME (KZeleznock for) NSalgado DATE 07/05/22 07/08/22 07/05/22 07/12/22