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EPID:L-2020-LLA-0132, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (Approved, Closed) |
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MONTHYEARML20198M4432020-07-16016 July 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Request to Modify Technical Specification 3.3.3-1 Post Accident Monitoring Instrumentation Project stage: Acceptance Review 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 Project stage: Request 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 Project stage: Other ML21084A1902021-05-0404 May 2021 Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation Project stage: Approval 2020-07-16
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Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection 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 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program 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 ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 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-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports 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 IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant 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 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan 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 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 IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) 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 ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23261B0192023-09-25025 September 2023 Aging Management Audit Plan Regarding the License Renewal Application Review ML23261C3642023-09-25025 September 2023 License Renewal Application Online Reference Portal ML23256A3592023-09-22022 September 2023 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Energy Harbor Nuclear Corp. Application for License Renewal IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report 2024-02-02
[Table view] Category:Safety Evaluation
MONTHYEARML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23019A0032023-03-16016 March 2023 Issuance of Amendment Nos. 320 and 210 Adoption of Technical Specifications Task Force (Tstf) Traveler Tstf-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23062A5212023-03-0606 March 2023 Issuance of Amendment No. 319 Revise Technical Specification (TS) 3.5.2, ECCS Operating, Limiting Condition for Operation (LCO) 3.5.2, 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 ML22269A3582022-11-15015 November 2022 Issuance of Amendment No. 305 Revising the Emergency Plan ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure ML22277A8142022-10-0707 October 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan 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 ML22222A0862022-09-0101 September 2022 Issuance of Amendment Nos. 317 and 208 Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation ML22235A7672022-09-0101 September 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22140A2092022-06-28028 June 2022 Issuance of Amendment No. 207 Correct TS 3.1.7 Change Made by TSTF-547 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) ML22147A1492022-06-0202 June 2022 Relief Request RP-3 Regarding Fuel Oil Transfer Pump Testing ML22136A1092022-05-24024 May 2022 Proposed Alternative Request RP-2 Regarding the Inservice Testing of Certain Pumps ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21286A7822022-05-0606 May 2022 Issuance of Amendment Nos. 315 and 205 Regarding Changes to the Emergency Plan ML22118B0382022-05-0505 May 2022 Proposed Alternative Request RP-4 Regarding the Inservice Testing of High-Pressure Injection Pumps ML22077A1342022-05-0202 May 2022 Issuance of Amendment Nos. 314 and 204 Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22096A3162022-04-12012 April 2022 Proposed Alternative Request RP-1 Regarding Digital Instrumentation for Inservice Testing ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 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' ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves 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 ML21153A1762021-06-30030 June 2021 Issuance of Amendment No. 201 Revision of Technical Specifications Related to Steam Generator Tube Inspection, and Repair Methods 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 ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor 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 ML20335A0522021-02-18018 February 2021 Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition 2024-01-17
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October 8, 2020 Mr. David B. Hamilton Executive Vice President and Chief Nuclear Officer Energy Harbor Corporation 168 E. Market Street Akron, OH 44308-2014
SUBJECT:
ENERGY HARBOR NUCLEAR CORP. - DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1; PERRY NUCLEAR POWER PLANT, UNIT NO. 1; AND BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2;- REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI (EPID L-2020-LLA-0132)
Dear Mr. Hamilton:
By application dated September 28, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20273A290), pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a, "Codes and standards," paragraph (g)(4)(iv), and U.S.
Nuclear Regulatory Commission (NRC) Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," Dated July 28, 2004, Energy Harbor Nuclear Corporation (Energy Harbor, the licensee) submitted a request to use a specific provision of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), Perry Nuclear Power Plant, Unit No. 1 (PNPP), and Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS). Specifically, Energy Harbor Nuclear Corp. requests approval to use IWA-4540(b) of the 2017 Edition of the ASME B&PV Code.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that Energy Harbor has adequately addressed the requirements in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff approves the use of subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI, for Davis-Besse Nuclear Power Station, Unit No. 1, Perry Nuclear Power Plant, Unit No. 1, and Beaver Valley Power Station, Unit Nos. 1 and 2. For each facility, this approval is for the remainder of the current 10-year inservice inspection interval, as specified in the application.
All other ASME BPV Code,Section XI, requirements which are not modified by the NrC staff approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
D. Hamilton If you have any questions, please contact Bhalchandra Vaidya at 301-415-3308 or via e-mail at Bhalchandra.Vaidya@nrc.gov.
Sincerely, Nancy L. Digitally signed by Nancy L. Salgado Date: 2020.10.08 10:57:58 -04'00' Salgado Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-412, 50-346, 50-440.
Enclosures:
Safety Evaluation cc: Listserv DAVIS-BESSE PERRY BEAVER VALLEY Terry J. Brown Frank R. Payne Rod L. Penfield Site Vice President Site Vice President Site Vice President Energy Harbor Nuclear Corp. Energy Harbor Nuclear Corp. Energy Harbor Nuclear Corp.
Davis-Besse Nuclear Power Station Perry Nuclear Power Plant Beaver Valley Power Station Mail Stop P-DB-3080 Mail Stop P-PY-A290 Mail Stop P-BV-SSB 5501 N. State Route 2 PO Box 97, P.O. Box 4, Route 168 Oak Harbor, OH 43449-9760 Perry, OH 44081-0097 Shippingport, PA 15077-0004
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE FOR ENERGY HARBOR NUCLEAR CORP.
ENERGY HARBOR NUCLEAR GENERATION LLC DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NOS. 50-346 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NOS. 50-440 BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By application dated September 28, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20273A290), Energy Harbor Nuclear Corporation (Energy Harbor, the licensee) submitted a request to use a specific provision of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), Perry Nuclear Power Plant, Unit No. 1 (PNPP), and Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),
Energy Harbor proposed to use subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI, in place of the corresponding subparagraph from the code of record at these facilities.
Enclosure
2.0 PROPOSED USE OF SUBSEQUENT CODE EDITION AND ADDENDA 2.1 Components for Which the Subsequent Code Edition is Requested All Class 1, 2, and 3 items located in the ASME BPV Code,Section XI, boundaries.
2.2 Current Code Requirement Subparagraph IWA-4540(b) provides items that are exempt from pressure testing after repair/replacement activities.
2.3 Current Code Edition and Addenda of Record The application identified the currently applicable editions and addenda of the ASME BPV Code,Section XI, for each plant, as shown in Table 1 below. In addition, Table 1 shows the associated 10-year inservice inspection (ISI) interval, including the start and end dates, for each plant.
Table 1: Current ASME BPV Code,Section XI, Code of Record ISI ASME BPV CODE, PLANT START END INTERVAL SECTION XI Beaver Valley Power 2013 Edition, No 5th 8/29/2018 8/28/2028 Station, Unit No. 1 Addenda Beaver Valley Power 2013 Edition, No 4th 11/5/2018 8/28/2028 Station, Unit No. 2 Addenda Davis-Besse Nuclear 2007 Edition, through Power Station, Unit 4th 9/21/2012 9/20/2022 2008 Addenda No. 1 Perry Nuclear Power 2013 Edition, No 4th 5/18/2019 5/17/2029 Plant, Unit No.1 Addenda 2.4 Proposed Subsequent Code Edition and Addenda The proposed subsequent Code edition and addenda to be used is subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI.
2.5 Duration of the Use of the Later Code Edition and Addenda The duration of this request is for the remainder of the current 10-year ISI interval for each plant, as shown in Table 1 above.
3.0 REGULATORY EVALUATION
The licensee is proposing to use a portion of a later edition and addenda of the ASME BPV Code,Section XI, in accordance with 10 CFR 50.55a(g)(4)(iv), which states:
Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of this section, subject to the conditions listed in
paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.
Given that 10 CFR 50.55(g)(4)(iv) permits the NRC staff to approve the use of subsequent editions and addenda of the ASME BPV Code,Section XI, the NRC staff finds that, subject to the following technical evaluation, the licensee may propose to use a portion of a later edition and addenda of the ASME BPV Code,Section XI, and the NRC staff has the regulatory authority to approve the use of a portion of a later edition and addenda of the ASME BPV Code,Section XI.
4.0 NRC TECHNICAL EVALUATION As previously stated in Section 3.0 of this safety evaluation, prior to approving the use of a subsequent edition and addenda of the ASME BPV Code under 10 CFR 50.55a(g)(4)(iv), the NRC staff must find that: (1) the proposed subsequent edition and addenda are incorporated by reference in 10 CFR 50.55a(a); (2) the licensee will comply with the conditions listed in 10 CFR 50.55a(b) that are applicable to the proposed edition and addenda of the ASME BPV Code; (3) the licensee requested approval to use the subsequent edition and addenda; and (4) if only portions of edition or addenda are to be used, all related requirements of the respective edition or addenda are met. If these criteria are met, the NRC staff can find the use of the subsequent edition and addenda of the ASME BPV Code,Section XI, to be acceptable.
4.1 Incorporation by Reference In evaluating the first criterion, 10 CFR 50.55a(b)(2) incorporates by reference the ASME BPV Code, 2017 Edition,Section XI, Division 1, as approved in Federal Register Notice, 85 FR 26540, dated May 4, 2020. The licensee proposed to use the 2017 Edition of Section XI, which is included in the list of editions and addenda incorporated by reference in the current edition of 10 CFR 50.55a(a). Therefore, the NRC finds that the first criterion has been satisfied.
4.2 Subject to Conditions Listed in 10 CFR 50.55a(b)
In evaluating the second criterion, the NRC staff finds that 10 CFR 50.55a(b) contains no conditions relevant to this request. Therefore, the NRC staff finds that the second criterion has been satisfied.
4.3 Requesting Commission Approval In evaluating the third criterion, the licensees request dated September 28, 2020, constitutes a request to the Commission for approval to use a subsequent edition or addendum of the ASME BPV Code. Therefore, the NRC staff finds that the third criterion has been satisfied.
4.4 All Related Requirements In evaluating the fourth criterion, the NRC staff finds that there are no related requirements relevant to this request. Therefore, the NRC staff finds that the fourth criterion has been satisfied.
4.5 Summary Based on the above evaluation, the NRC staff finds that the licensee has adequately addressed all regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv).
5.0 CONCLUSION
As set forth above, the NRC staff finds that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff finds that the use of subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI, is acceptable. The NRC staff approves the use of subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI, at Davis-Besse Nuclear Power Station, Unit No. 1, Perry Nuclear Power Plant, Unit No. 1, and Beaver Valley Power Station, Unit Nos. 1 and 2.
For each facility, this approval is for the remainder of the current 10-year ISI interval, as listed in Table 1 above.
All other ASME BPV Code,Section XI, requirements which are not modified by the NRC staffs approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Bhalchandra K. Vaidya, NRR Date: October 8, 2020
ML20279A440 (*) By Email OFFICE NRR/DORL/LPL3/PM* NRR/DORL/LPL3/LA* NRR/DNRL/NPHP/BC*
NAME BVaidya SRohrer MMitchell DATE 10/06/2020 10/05/2020 10/06/2020 OFFICE NRR/DORL/LPL3/BC* NRR/DORL/LPL3/PM*
NAME NSalgado BVaidya DATE 10/08/2020 10/08/2020