Similar Documents at Perry |
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Category:Code Relief or Alternative
MONTHYEARML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22252A2212022-09-30030 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 ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 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) 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 2024-09-13
[Table view] Category:Letter
MONTHYEARML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 12024-09-16016 September 2024 License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1 ML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML24256A0872024-09-11011 September 2024 Fws to NRC, Concurrence with Endangered Species Act Nlaa Determinations for Perry License Renewal L-24-201, Spent Fuel Storage Cask Registration2024-09-0909 September 2024 Spent Fuel Storage Cask Registration ML24249A0762024-09-0606 September 2024 Letter to Douglas Lankford, Chief_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0862024-09-0606 September 2024 Letter to Regina Gasco-Bentley, Chairperson_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24166A0172024-09-0606 September 2024 Ltr. to Glenna Wallace, Chief, Eastern Shawnee Tribe of Oklahoma; Re., NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0782024-09-0606 September 2024 Ltr. to Kenneth Meshigaud, Chairperson, _ Re., NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0752024-09-0606 September 2024 Letter to Charles Diebold, Chief_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24250A0412024-09-0606 September 2024 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 ML24249A0882024-09-0606 September 2024 Letter to Rickey Armstrong, President_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24247A0212024-09-0606 September 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Perry License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2024-0006782) L-24-200, License Renewal Application for Revision to Supplement 4 for Editorial Corrections2024-09-0505 September 2024 License Renewal Application for Revision to Supplement 4 for Editorial Corrections ML24228A1702024-09-0303 September 2024 Ltr to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-Notice of Avail of the Draft Supp 61 to the GEIS for License Renew of Nuclear Plants ML24228A1712024-09-0303 September 2024 Ltr to Brian Dickens, EPA-Perry Nuclear Power Plant Unit 1-Notice of Avail of the Draft Supp 61 to the GEIS for License Renew of Nuclear Plants L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24240A1482024-08-27027 August 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-24-190, Spent Fuel Storage Cask Registration2024-08-26026 August 2024 Spent Fuel Storage Cask Registration ML24239A7782024-08-26026 August 2024 Aging Management Audit - Perry Unit 1 - License Renewal Application August 26 2024 IR 05000440/20240052024-08-22022 August 2024 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2024005) L-24-174, Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information2024-08-15015 August 2024 Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 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 L-24-168, Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage2024-07-15015 July 2024 Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage 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 L-24-155, Reactor Water Clean Up Leak Detection Loss of Safety Function2024-06-27027 June 2024 Reactor Water Clean Up Leak Detection Loss of Safety Function L-24-140, Operation of the Residual Heat Removal Loops B and C Alternate Keep Fill Configuration Was Prohibited by Technical Specifications and Resulted in an Unanalyzed Condition2024-06-20020 June 2024 Operation of the Residual Heat Removal Loops B and C Alternate Keep Fill Configuration Was Prohibited by Technical Specifications and Resulted in an Unanalyzed Condition 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-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report ML24095A3282024-04-19019 April 2024 License Renewal Revised Schedule Letter 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 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 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 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML23353A0012024-02-21021 February 2024 – Issuance of Amendment No. 202 to Adopt TSTF-276, Revision 2, Revise DG Full Load Rejection Test ML23292A2972023-11-17017 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 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 2024-09-13
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 29, 2018 Mr. David B. Hamilton Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -APPROVAL OF ALTERNATIVE TO USE BWRVIP GUIDELINES IN LIEU OF CERTAIN ASME CODE REQUIREMENTS (CAC NO. MG0149; EPID 2017-LLR-0112) (L-17-183)
Dear Mr. Hamilton:
By letter dated September 29, 2017, FirstEnergy Nuclear Operating Company (FENOC) submitted a request in accordance with paragraph 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for Perry Nuclear Power Plant, Unit 1 (PNPP).
Specifically, pursuant to 10 CFR 50.55a(z)(1 ), FENOC requested to use Boiling Water Reactor Vessel and Internals Project inspection and evaluation guidelines, in lieu of specific ASME Code,Section XI, requirements for the reactor pressure vessel internals and component inspections, on the basis that the alternative provides an acceptable level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRG) staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the proposed alternatives, as described in relief request IR-056, Revision 2, provide an acceptable level of quality and safety. Accordingly, the NRG staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ).
The NRG authorizes the use of proposed alternatives for PNPP until the end of the third 10-year inservice inspection interval which ends on May 17, 2019.
All other requirements of ASME Code,Section XI, for which relief was not specifically requested and authorized by the NRG staff remain applicable, including the third-party review by the Authorized Nuclear In-service Inspector.
D. Hamilton If you have any questions, please contact Kimberly Green at (301) 415-1627.
Sincerely, C)J(} 1/__..,
David J. Wrona, £;anch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Safety Evaluation cc: ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO 10 CFR 50.55a REQUEST FOR ALTERNATIVE TO APPLY BWRVIP INSPECTION AND EVALUATION GUIDELINES FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION, LLC PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated September 29, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17272A093), FirstEnergy Nuclear Operating Company (FENOC, the licensee), submitted a relief request, IR-056, Revision 2, to apply alternative examination methods to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, inservice inspection (ISi) Class 1 components at the Perry Nuclear Power Plant, Unit 1 (PNPP).
Specifically, pursuant to Title 1O of the Code of Federal Regulations (1 O CFR), paragraph 50.55a(z)(1 ), the licensee requested to use certain Boiling Water Reactor Vessel and Internals Project (BWRVIP) inspection and evaluation (l&E) guidelines, in lieu of specific ASME Code,Section XI, requirements for the reactor pressure vessel internals and component inspections (i.e., vessel interior, interior attachments within beltline region, interior attachments beyond beltline region, and core support structure), on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
Adherence to Section XI of the ASME Code is mandated by 10 CFR 50.55a(g)(4), which states, in part, that ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI.
Regulation 10 CFR 50.SSa(z) states that "[a]lternatives to the requirements of paragraphs (b) through (h) of section or portions thereof may be used when authorized by the Director, Office of Nuclear Reactor Regulation, or Director, Office of New Reactors, as appropriate. A proposed alternative must be submitted and authorized prior to implementation. The applicant or licensee must demonstrate that: (1) Acceptable level of quality and safety. The proposed alternative would provide an acceptable level of quality and safety; or (2) Hardship without a compensating Enclosure
increase in quality and safety. Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request the use of an alternative and the NRC to authorize the proposed alternative.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Request for Alternative 3.1.1 ASME Code Component Affected ASME Code,Section XI, Class 1, Examination Category B-N-1 (Interior of Reactor Vessel), and B-N-2 (Welded Core Support Structures and Interior Attachments to Reactor Vessels), item numbers:
- 813.20 - Vessel Interior Attachments within Beltline Region
- 813.30 - Interior Attachments beyond Beltline Region
- 813.40 - Core Support Structure
- 3. 1.2 Applicable Code Edition and Addenda Section XI, of ASME Code, 2001 Edition through the 2003 Addenda 3.1.3 Applicable Code Requirement Section XI of the ASME Code, requires the visual examination {VT) of certain reactor vessel internal (RVI) components. These examinations are included in Table IWB-2500-1, Categories B-N-1 and 8-N-2, and are identified with the following item numbers:
- 813.1 O - Examine accessible areas of the RV interior each inspection period using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI
- 813.20 - Examine accessible interior attachment welds within the beltline region each interval using a technique which meets the requirements for a VT-1 examination as defined in paragraph IWA-2211 of the ASME Code,Section XI
- 813.30 - Examine accessible interior attachment welds beyond the beltline region each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI
- B 13.40 - Examine accessible surfaces of the core support structures each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI 3.1.4 Reason for Request As an alternative to the ASME Code inspection requirements, use of BWRVIP l&E guidelines will avoid unnecessary inspections, while reducing radiological dose.
3.1.5 Proposed Alternative The licensee proposes to apply the BWRVIP l&E guidelines listed below to affected ASME Code components identified in Table 1 of its submittal, in lieu of the requirements of ASME Code,Section XI, paragraph IWB-2500(a), and Table IWB-2500-1, including the examination method, examination volume, frequency, training, successive and additional examinations, flaw evaluations, and reporting.
- BWRVIP-25, "BWR Core Plate Inspection and Flaw Evaluation Guidelines"
- BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines"
- BWRVIP-38, "BWR Shroud Support Inspection and Flaw Evaluation Guidelines"
- BWRVIP-41, Revision 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines"
- BWRVIP-47-A, "BWR Lower Plenum Inspection and Flaw Evaluation Guidelines"
- BWRVIP-48-A, "Vessel ID [Internal Diameter] Attachment Weld Inspection and Flaw Evaluation Guidelines"
- BWRVIP-76, Revision 1-A, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines" (see note)
- BWRVIP-94NP, Revision 2, "BWR Vessel and Internals Project Program Implementation Guide"
- BWRVIP-100, Revision 1-A, "Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds"
- BWRVIP-138, Revision 1-A, "Updated Jet Pump Beam Inspection and Flaw Evaluation"
- BWRVIP-180, "BWR Vessel and Internals Project, Access Hole Cover Inspection and Flaw Evaluation Guidelines"
- BWRVIP-183-A, "Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines" Note: If flaw evaluations are required for BWRVIP-76 examinations, the fracture toughness values of BWRVIP-100 will be utilized.
The licensee stated that any deviations from the referenced BWRVIP l&E guidelines for the duration of the proposed alternative will be appropriately documented and communicated to the NRG, per the BWRVIP Deviation Disposition Process. Furthermore, FENOC stated that PNPP does not currently have any deviations from the subject guidelines.
3.1.6 Basis for Use Licensees of boiling-water reactors (BWRs) examine reactor internals in accordance with BWRVIP guidelines. These guidelines were written to address the safety significant vessel internal components and to examine and evaluate the examination results for these components using appropriate methods and reexamination frequencies. The BWRVIP has established a reporting protocol for examination results and deviations.
The 8WRVIP recommended examinations specify locations that are known to be vulnerable to 8WR relevant degradation mechanisms rather than "all surfaces." The 8WRVIP examination methods (including an enhanced visual examination VT-1 [EVT-1] or ultrasonic test [UT]) are superior to the ASME Code required VT-3 for flaw detection and characterization. In most cases, the 8WRVIP examination frequency is equivalent to or more frequent than the examination frequency required by the ASME Code. In cases where the 8WRVIP examination frequency is less frequent than required by the ASME Code, the 8WRVIP examinations are performed in a more comprehensive manner and focus on areas that are most vulnerable.
The enhanced flaw detection and characterization capability, with an equivalent or more frequent examination frequency, or with a less frequent examination frequency but with those examinations being performed in a more comprehensive manner, and using comparable flaw evaluation criteria, results in the 8WRVIP criteria providing a level of quality and safety that is equivalent to or exceeds that provided by the ASME Code requirements. Thus, the licensee determined that use of these 8WRVIP guidelines as alternatives to the ASME Code requirements provide an acceptable level of quality and safety.
The 8WRVIP executive committee periodically revises the 8WRVIP l&E guidelines to include enhancements in inspection techniques and flaw evaluation methodologies. Where the revised version of a 8WRVIP guideline continues to also meet the requirements of the version of the 8WRVIP guideline that forms the safety basis for the NRG-authorized proposed alternative to the requirements of 10 CFR 50.55a, it may be implemented. Otherwise, the revised guidelines will only be implemented after NRG approval of the revised 8WRVIP guidelines or a plant-specific request for an alternative has been authorized.
The licensee provided with its submittal a comparison of ASME Code,Section XI, Examination Category 8-N-1 and 8-N-2 requirements with 8WRVIP guidance requirements which provides specific examples comparing the inspection requirements of ASME Code,Section XI, item numbers 813.10, 813.20, 813.30, and 813.40 in Table IW8-2500-1, to the inspection requirements in the 8WRVIP documents, including inspection methods. Furthermore, the licensee provided specific examples of how the l&E guidelines from various 8WRVIP reports compare to the ASME Code requirements with respect to inspection scope, examination method, and frequency.
3.1. 7 Duration of Proposed Alternative The alternative is requested for the balance of the third 10-year ISi interval, which expires on May 17, 2019.
3.2 NRG Staff Evaluation The NRG staff found the referenced 8WRVIP reports identified in the licensee's submittal to be acceptable for use because the l&E guidelines addressed in these reports would identify degradation in a timely manner and ensures that the integrity of the RVI components will be maintained. In addition, PNPP compliance with inspection criteria included in the reports would provide reasonable assurance that age related degradation in the RVI components will be identified in a timely manner.
Specifically, 8WRVIP-18 (Revision 2-A), 8WRVIP-26-A, 8WRVIP-27-A, 8WRVIP-47-A, 8WRVIP-48-A, 8WRVIP-76 (Revision 1-A), 8WRVIP-100, (Revision 1-A), 8WRVIP-138 (Revision 1-A), and 8WRVIP-183-A, have been previously reviewed and approved by the NRG
staff with a corresponding safety evaluation (SE) attached to each of the "-A" reports. Although BWRVIP-25 and BWRVIP-38 do not have a corresponding "-A" report, they were reviewed and approved by the NRC staff by letters dated December 19, 1999, and July 24, 2000, respectively.
The BWRVIP-41 and BWRVIP-42 l&E guidelines were previously reviewed and approved by the NRC staff with a corresponding SE attached to each of the "-A" reports. These two reports (BWRVIP-41 and BWRVIP-42) have since been updated, and the revisions identified in the licensee's submittal continue to incorporate adequate l&E guidelines to detect degradation in the stated components. The staff authorizes the use of the BWRVIP l&E guidelines, discussed above, in lieu of ASME requirements for the stated components because the inspection techniques that are recommended by the BWRVIP meet or exceed the inspection techniques mandated by the ASME Code,Section XI, ISi program. In addition, the BWRVIP l&E guidelines provide inspection frequencies sufficient to detect aging degradation; therefore, subsequent inspections of the RVI components per the relevant BWRVIP l&E guidelines will provide reasonable assurance that any emerging aging effects will be identified in a timely manner and provides an acceptable level of quality and safety.
The BWRVIP-180 l&E guideline has not been submitted to the NRC for review and approval; however, the l&E guideline meets or exceed the inspection frequency and techniques mandated by the ASME Code,Section XI, ISi program, and degradation can be identified in a timely manner and ensures that the integrity of the RVI components will be maintained; thus, the staff authorizes the use of this report in lieu of ASME Code requirements for the stated components.
In addition, the staff notes that BWRVIP-03 and BWRVIP-94NP, Revision 2, do not contain l&E guidelines for any specific components. Rather, BWRVIP-03, in general: (1) provides an overview of the structure of the BWRVIP, and (2) includes guideline documents that establish protocols to follow in order to gain access to BWRVIP-owned mockups; to perform formal demonstrations of nondestructive examinations (NOE) techniques using BWRVIP mockups; and to perform their own demonstrations of NOE techniques or inspection tooling in an acceptable manner. Furthermore, BWRVIP-94NP, Revision 2, establishes a framework for structuring and strengthening existing BWR vessel and internals programs to ensure consistent application of guidelines by BWRVIP members.
As part of its evaluation of this alternative request, the NRC staff reviewed the results of the reactor internals inspection history up until the most recent inspections in 2015 for PNPP that were available. These results were referenced by the licensee as supporting information in its submittal and provide information regarding inspection methods used on the RVI components, inspection dates, the inspection results, and corrective actions related to the inspection findings.
These results are documented in a letter submitted by the Electric Power Research Institute, "Project No. 704-BWR Vessel and Internals Inspection Summaries for Spring 2015 Outages,"
dated May 23, 2016 (ADAMS Accession No. ML16152A162).
Based on its review of these inspection summaries for PNPP, the NRC staff finds that the licensee has adequately demonstrated its capability in: (1) identifying the weld flaws (cracking);
(2) taking appropriate corrective actions to ensure that the structural integrity of the component is maintained (i.e., proper repair (if necessary), or flaw evaluation with proper engineering justification); and (3) complying with scope expansion of inspections and subsequent inspections per the applicable BWRVIP reports.
Based on the above considerations, the NRC staff finds that the implementation of the BWRVIP l&E guidelines specified in the licensee's proposed alternative will ensure that the integrity of the RVI components will be maintained with an acceptable level of quality and safety.
The NRC staff acknowledges that the BWRVIP Executive Committee periodically revises the BWRVIP guidelines to include enhancements in inspection techniques and flaw evaluation methodologies. While the licensee may choose to implement enhancements described in a revised version of a BWRVIP l&E guideline, the licensee must continue to also meet the requirements of the version of the BWRVIP l&E guideline that forms the basis for the NRC staff's authorized alternative to the requirements of 10 CFR 50.55a. The licensee may also choose to return to complying with the inspection requirements of the ASME Code of Record for PNPP.
Thus, the NRC staff authorizes only the BWRVIP l&E guidelines proposed as an alternative in this relief request. In the event the licensee decides to take exceptions to, or deviations from, the authorized alternative, the licensee must revise and resubmit its request for authorization to use the proposed alternative under 10 CFR 50.SSa(z).
4.0 CONCLUSION
As set forth above, the NRC staff determines that the licensee-proposed alternatives, as described in request IR-056, Revision 2, provide an acceptable level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, the NRC staff authorizes the licensee-proposed alternatives, as described in request IR-056, Revision 2, for the remainder of the third 10-year ISi interval at PNPP.
All other requirements of ASME Code,Section XI, for which relief was not specifically requested and authorized by the NRC staff remain applicable, including the third-party review by the Authorized Nuclear In-Service Inspector.
Principal Contributor: 0. Yee, NRA Date of issuance: January 29, 2018
D. Hamilton
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -APPROVAL OF ALTERNATIVE TO USE BWRVIP GUIDELINES IN LIEU OF CERTAIN ASME CODE REQUIREMENTS (CAC NO. MG0149; EPID 2017-LLR-0112) (L-17-183)
DATED JANUARY 29, 2018 DISTRIBUTION:
PUBLIC RidsAcrs_MailCTR Resource RidsNrrDorlLpl3 Resource RidsNrrDmlrMvib Resource RidsNrrPMPerry Resource RidsNrrLASRohrer Resource RidsRgn3MailCenter Resource OYee, NRR ADAMS A ccess1on No. ML18023A625 *b1yemail OFFICE NRR/D0RL/LPL3/PM NRR/D0RL/LPL3/LA NRR/DMLR/MVI 8/BC NRR/D0RL/LPL3/BC NAME KGreen SRohrer SRuffin (A)* DWrona DATE 01/23/2018 01/23/2018 10/26/2017 01/29/2018 OFFICIAL RECORD COPY