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] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 8, 2009 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry,OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO.1 - RELIEF REQUEST PR-3 FOR THIRD 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. ME0820)
Dear Mr. Bezilla:
By letter to the Nuclear Regulatory Commission (NRC) dated February 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML0906506680),
FirstEnergy Nuclear Operating Company (FENOC), the licensee, submitted Relief Request PR-3 for the third 1O-year interval inservice testing (1ST) program at Perry Nuclear Power Plant.
The licensee requested approval to use Code Case OMN-18 of the American Society of Mechnical Engineers (AS ME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), with modifications, for certain pumps in the 1ST program at Perry. By letter dated June 9,2009 (ADAMS Accession No. ML091670464), FENOC submitted additional information pertaining to the relief request.
The NRC staff has completed its review of this relief request. The details of the NRC staff's review are included in the enclosed safety evaluation. The NRC staff concludes that the licensee's proposed alternative provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the licensee-proposed alternative to use Code Case OMN-18 of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code), with modifications, for certain pumps in the 1ST program at Perry.
Use of ASME Code Case OMN-18 is authorized until such time as ASME Code Case OMN-18 is published in a future version of Regulatory Guide (RG).1.192 and incorporate by reference in 10 CFR 50.55a(b). At that time, if the licensee intends to continue implementing this ASME Code Case, it must follow all provisions of ASME Code Case OMN-18 with conditions as specified in RG 1.192 and limitations as specified in 10 CFR 50.55a(b)(4), (b)(5), and (b)(6), if any.
M. Bezilla -2 If you have any questions, please contact the Perry Project Manager, Mr. Stephen Sands, at 301-415-3154.
Sincerely,
~GtW Stephen J. Campbell, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
As stated cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST FOR PUMP AND VALVE INSERVICE TESTING PROGRAM FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO.1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated February 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML0906506680), FirstEnergy Nuclear Operating Company (FENOC),
the licensee, submitted Relief Request PR-3 for approval to use a modified Code Case OMN-18 of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the inservice testing (1ST) program at Perry Nuclear Power Plant (Perry). By letter dated June 9, 2009, the licensee submitted additional information pertaining to the relief request (ADAMS Accession No. ML091670464). The licensee requested approval for Perry's third 10-year 1ST interval, which begins on May 18, 2010.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, requires that 1ST of certain ASME Code Class 1,2, and 3 pumps and valves be performed at 120-month (10-year) 1ST program intervals in accordance with the specified ASME Code and applicable addenda incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Nuclear Regulatory Commission (NRC) pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month 1ST program interval. In accordance with 10 CFR 50.55a(f)(4)(iv), 1ST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. NRC guidance contained in Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," provides alternatives to ASME Code requirements which are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482 Revision 1, "Guidance for Inservice Testing at Nuclear Power Plants." ASME OM code cases that are approved for use by the NRC are listed in Regulatory Guide (RG) 1.192, "Operation and Maintenance C0de Case Acceptability, ASME OM Code" dated June 2003.
The NRC's findings with respect to granting or denying the 1ST program relief request are given below:
ENCLOSURE
-2
3.0 TECHNICAL EVALUATION
3.1 Affected Components Pump Description Class Current Classification 1C41-C001 A&B Standby Liquid Control 2 Group B 1E12-C002A & Residual Heat Removal 2 Group A B (RHR) A and B 1E12-C002C RHRC 2 Group B 1E21-C001 Low Pressure Core 2 Group B Spray 1E22-C001 High Pressure Core 2 Group B Spray (HPCS) 1E51-C001 Reactor Core Isolation 2 Group B Cooling G41-C003A & B Fuel Pool Cooling and 3 Group A Cleanup 1P42-C001A & Emergency Closed 3 Group A B Cooling Water
'I P45-C001A & Emergency Service 3 Group A B Water 1P45-C002 HPCS Emergency 3 Group B Service Water P47-C001A & B Control Complex Chilled 3 Group A Water
'I R45-C001A, B, Fuel Oil Transfer #1 3 Group B
&C 1R45-C002A, B, Fuel Oil Transfer #2 3 Group B
&C 3.2 Applicable Code The applicable ASME OM Code edition and addenda for Perry is the 2001 Edition with Addenda through OMb-2003.
ISTB-2000, "Supplemental Definitions," defines operating criteria for designating Group A and Group B pumps.
ISTB-3000, "General Testing Requirements," and Table ISTB-3000-1, "Inservice Test Parameters," define and compare parameters (e.g., pressure flow rate, vibration) measured during Group A, Group B, and Comprehensive pump tests.
ISTB-3400, "Frequency of Inservice Tests," states that an inservice test shall be run on each pump as specified in Table ISTB-3400-1. This table requires a Group A or Group B test to be performed quarterly and a Comprehensive test to be performed biennially.
Table ISTB-3500-1, "Required Instrument Accuracy," defines the required instrument accuracy for Group A, Group B, Comprehensive, and Preservice tests.
-3 Table 18TB-51 00-1, "Centrifugal Pump Test Acceptance Criteria," defines the required acceptance criteria for Group A, Group B, and Comprehensive tests for centrifugal pumps.
Table 18TB-5200-1, "Vertical Line 8haft and Centrifugal Pumps Test Acceptance Criteria,"
defines the required acceptance criteria for Group A, Group B, and Comprehensive tests for vertical line shaft pumps.
Table 18TB-5300-2, "Reciprocating Positive Displacement Pump Test Acceptance Criteria,"
defines the required acceptance criteria for Group A, Group B, and Comprehensive tests for reciprocating positive displacement pumps.
3.3 Licensee's Basis for Requesting Relief The licensee states:
The A8ME OM Code Committee has established Code Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly Within +/- 20% of Design Flow." This code case has not yet been approved for use in RG 1.192, "Operation and Maintenance Code Case Acceptability, A8ME OM Code," June 2003. Although Code Case OMN-18 has not been approved for use, FENOC is proposing this alternative for Group A (and Group B re-c1assified as Group A) pumps.
The increased requirements imposed by the proposed alternative on the parameters to be monitored during every quarterly pump test, and the more accurate instruments that must consistently be used during quarterly testing of pumps classified Group A (and Group B pumps that are re-classified as Group A pumps), allows FENOC to perform better trending of pump performance data due to the more consistent requirements for each of the quarterly tests.
Due to the increased requirements on the parameters imposed by the proposed alternative during all quarterly tests, there is no added value in performing the biennial comprehensive test.
3.4 Licensee's Proposed Alternative Testing The licensee states:
FENOC proposes that in lieu of the requirements of 18TB-3400, Group A tests will be performed quarterly within +/- 20 percent of the pump design flow rate, with instrumentation meeting the instrument accuracy requirements of Table 18TB-3500-1 for the biennial Comprehensive test, and the Comprehensive test would not be required.
8pecifically,
- a. Pumps tested quarterly using this alternative must be tested within +/- 20 percent of pump design flow, as is required for the biennial comprehensive test in 18TB-3300(e) and (f).
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- b. The proposed alternative requires the accuracy of instruments used during quarterly Group A tests to meet the more accurate pressure and differential pressure requirements listed for the Comprehensive test in Table IST8-3500-1 (an accuracy improvement from +/- 2 percent to +/- 0.5 percent). Consistent use of these more accurate instruments during each quarterly test provides for improved Group A pump performance trend data evaluation.
- c. Pumps that would normally be categorized as Group 8 pumps, but are re categorized as Group A, may be tested according to the provisions of this alternative.
As a result of this re-categorization from Group 8 to Group A, per Table IST8-3000-1, additional data must be obtained quarterly rather than once every 2 years on the test parameters of:
- Vibration (for all the affected pumps).
- d. Use of this alternative provides for consistent acceptance criteria for pump flow and differential pressure tests. FENOC will consistently utilize the Group A test acceptance criteria in Tables IST8-51 00-1, IST8-5200-1, and IST8-5300-2 for pump tests rather than having to utilize the comprehensive test criterion for one biennial test.
The licensee stated in a letter dated June 9, 2009:
8ased on recent guidance from the ASME OM Code Committee regarding application of Code Case OMN-18, the update of the 1ST Program for the third ten-year interval will reflect a more limiting upper bound Acceptable Range value of 1.06 versus 1.10 for flow and differential pressure. Values above 1.06 would be considered to be in the Required Action Range. This tightened Acceptable Range, in conjunction with using more accurate pressure instruments during testing (an accuracy improvement from +/- 2 percent to +/- 0.5 percent), provides more consistent trend results when comparing sUbsequent tests or test results in aggregate. Due to the improved accuracy, consistent testing methodology, and the addition of quarterly vibration monitoring, deviations in actual pump performance indicative of impending degradation are more easily recognized during quarterly performance trending activities. Additionally, declaring pumps inoperable for reasons other than actual equipment degradation can be avoided.
As detailed in IST8-5100-1, the ASME Code does not require utilization of an Alert Range for quarterly pump tests. As stated above, the proposed quarterly testing methodology is expected to more accurately identify deviations and trends in actual pump performance without relying on the use of a specified Alert Range.
-5 3.5 NRC Staff Evaluation The licensee is proposing to re-c1assify the Group 8 pumps listed in Section 3.1 above as Group A pumps, and perform 1ST for all the pumps listed in Section 3.1 in accordance with modified Group A test procedure.
The ASME OM Code requires that for Group 8 pumps, a Group 8 test is performed every quarter, and a comprehensive test is performed biennially. The Group 8 test is performed within +/- 20 percent of the pump design flow rate (if practicable), the pressure instrument accuracy is +/- 2 percent, and the upper limit for the Acceptable Range for flow rate or differential pressure is 110 percent of the reference values. The comprehensive test is performed within
+/- 20 percent of the pump design flow rate, the pressure instrument accuracy is +/- 0.5 percent, and the upper limit of the Acceptable Range for flow rate and differential pressure is 103 percent of the reference values. Vibration monitoring is only performed during the comprehensive test.
The licensee proposes that for Group A pumps, a modified quarterly test be performed every quarter, and the biennial comprehensive test is not required. The modified Group A quarterly test would be performed within +/- 20 percent of the pump design flow rate, using the more accurate pressure instrumentation that is required for a comprehensive test (+/- 0.5 percent versus +/- 2 percent). This modified quarterly test would replace the comprehensive test. The Acceptable Range for the modified Group A quarterly test is tighter than the range for the Group A quarterly test.
The licensee is proposing to perform a modified Group A pump test every quarter and not perform a comprehensive pump test. The licensee will use a more limiting upper bound of 106 percent for the Acceptable Range for flow and differential pressure in lieu of 110 percent that is required by the OM Code for Group A tests. This proposed upper bound of 106 percent is greater than the upper bound of 103 percent for the biennial comprehensive pump test. The pumps that will be reclassified from Group 8 to Group A will now have vibration monitoring performed quarterly. The OM Code does not require vibration monitoring for Group 8 pump tests. All of the pump tests will be performed with pressure gauges with 0.5 percent accuracy.
For the pumps that are currently classified as Group A, the elimination of the comprehensive pump test (with its more limiting Acceptable Range upper bound of 103 percent) is compensated for by using more accurate pressure gauges on every quarterly test. This will provide for better trending of pump performance. Instead of performing seven tests with pressure gauges with 2 percent accuracy, and then performing the eighth test with pressure gauges with 0.5 percent accuracy, all eight tests will be performed with the same 0.5 percent accurate gauges. For the Group 8 pumps that will be re-c1assified as Group A pumps, the elimination of the comprehensive pump test is compensated for by using a tighter Acceptance Range on the quarterly tests, by using more accurate pressure gauges on every quarterly test, and by performing vibration monitoring on every quarterly test. This will provide for better trending of pump performance. Instead of performing seven tests with pressure gauges with 2 percent accuracy, with no vibration monitoring, and then performing the eighth test with pressure gauges with 0.5 percent accuracy, all eight tests will be performed with pressure gauges with the same 0.5 percent accuracy, all eight tests will include vibration monitoring, and seven of the eight tests will have a tighter Acceptable Range. The proposed alternative would provide reasonable assurance of the operational readiness of the pumps listed in Section 3.1.
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4.0 CONCLUSION
Based on the above evaluation, the NRC staff concludes that the licensee's proposed alternative to the Code Group A and Group B testing requirements for the pumps listed in section 3.1 above are authorized pursuant to 10 CFR 50.55a(a)(3)(i), on the basis that the alternative provides an acceptable level of quality and safety. The licensee's proposed alternative provides reasonable assurance of the operational readiness of the pumps. The alternative is authorized for the third 10-year 1ST program interval.
Use of ASME Code Case OIVlN-18 is authorized until such time as ASME Code Case OMN-18 is published in a future version of RG.1.192 and incorporate by reference in 10 CFR 50.55a(b).
At that time, if the licensee intends to continue implementing this ASME Code Case, it must follow all provisions of ASME Code Case OMN-18 with conditions as specified in RG 1.192 and limitations as specified in 10 CFR 50.55a(b)(4), (b)(5), and (b)(6), if any.
Principal Contributor: RWolfgang, NRR Date: October 8, 2009
M. Bezilla -2 If you have any questions, please contact the Perry Project Manager, Mr. Stephen Sands, at 301-415-3154.
Sincerely, IRA!
Stephen J. Campbell, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
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