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MONTHYEARML23230A0012023-09-15015 September 2023 – Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations Project stage: Other 2023-09-15
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Category:Letter
MONTHYEARML25014A3082025-01-21021 January 2025 Transmittal Letter for VC Summer SE for SLRA Review ML25020A0342025-01-20020 January 2025 Special Report 2025-002 for Virgil C. Summer Nuclear Station, Unit 1, Inoperable Radiation Monitoring Instrumentation Channel ML25007A2342025-01-17017 January 2025 Limited Scope Aging Management Audit Report Regarding the Subsequent License Renewal Application Review ML25021A0612025-01-16016 January 2025 Special Report 2025-001 for Virgil Summer Nuclear Station, Unit 1, Inoperable Loose-Part Monitoring System Channel ML25013A1892025-01-15015 January 2025 Requalification Inspection Corporate Notification Letter ML24366A0302025-01-13013 January 2025 Regulatory Audit in Support of License Request for Proposed Changes to the License and Technical Specifications to Facilitate Service Water Piping Repair ML24365A1982024-12-30030 December 2024 Units and 2 - Request for Approval of Alternative Request V-2 Use of Mechanical Agitation for Back Leakage Testing of Accumulator Discharge Check Valves ML24344A1902024-12-23023 December 2024 Summary of Safety Inspection of the Service Water Reservoir Dam (CAC Nos. 001370/05000395; EPID L-2017-LNS-0015) (Nonproprietary Cover Letter) ML24340A1572024-12-0404 December 2024 Annual Commitment Change Summary Report 05000395/LER-2024-003, Common Cause Inoperability of Engineered Safety Features2024-11-18018 November 2024 Common Cause Inoperability of Engineered Safety Features ML24324A0022024-11-18018 November 2024 Steam Generator Tube Inspection Reports for the Unit 1 Fall 2022 and the Unit 2 Spring 2023 Refueling Outages ML24318C4622024-11-13013 November 2024 Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - License Amendment Nos. 315 and 315 Updated Information Regarding TSC Ventilation Design IR 05000280/20240032024-11-12012 November 2024 Integrated Inspection Report 05000280-2024003 and 05000281-2024003 ML24278A2832024-11-0707 November 2024 Letter to E. Carr Environmental Impact Statement Scoping Summary Report for Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20240032024-11-0606 November 2024 – Integrated Inspection Report 05000395/2024003 ML24305A1302024-10-31031 October 2024 Submittal of 30 Day Report Per 10 CFR 26.719(c) Blind Performance Testing ML24308A0052024-10-28028 October 2024 10-28-24 NRC V.C. Summer Nuclear Station SLR Cherokee Nation Letter to USNRC ML24308A0062024-10-25025 October 2024 Subsequent License Renewal Application Area of Potential Effect (Ape) Clarification Fairfield County, South Carolina SHPO Project No. 22-EJ0147 ML24302A1442024-10-24024 October 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 4 and Requested Information Formation in Response to Limited Aging Management Audit ML24250A0782024-10-22022 October 2024 Relief Request RR-5-V1 Regarding Service Water Return Header Check Valves ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps ML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System ML24290A1052024-10-0707 October 2024 Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20244032024-10-0303 October 2024 Cyber Security Inspection Report 05000280-2024403 and 05000281-2024403 Cover Letter (Public) IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24269A2182024-09-24024 September 2024 Updated Final Safety Analysis Report - Revision 56 ML24221A2112024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0592024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0542024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0642024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0552024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 2025-01-21
[Table view] Category:Safety Evaluation
MONTHYEARML25021A2282025-01-21021 January 2025 Final Safety Evaluation to the SLRA of Virgil C. Summer Nuclear Station, Unit 1 ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 – Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 – Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23061A0122023-05-0909 May 2023 Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23100A0652023-04-25025 April 2023 Issuance of Amendment Nos. 310 and 310, Regarding Turbine Building Tornado Classification ML23102A2832023-04-25025 April 2023 ASME OM Code Inservice Testing Program Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML23062A7292023-03-31031 March 2023 Deferral of Pressurizer and Steam Generator Weld Examinations ML23030B8472023-03-10010 March 2023 Issuance of Amendment Nos. 309 and 309, License Amendment Request Regarding a 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability ML23012A0152023-02-21021 February 2023 Issuance of Amendment No. 224 to Change Nozzle Blockage Testing Requirement for Reactor Building Spray System ML22341A1972022-12-15015 December 2022 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval ML22244A1722022-09-22022 September 2022 Issuance of Amendment No. 223 to Relocate Main Steam Isolation Valve Isolation Times to the Updated Final Safety Analysis Report ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21319A2622021-12-28028 December 2021 Issuance of Amendment No. 220 to Relocate Unit Staff Qualifications from Technical Specification to Quality Assurance Program Description ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines ML21188A3322021-08-10010 August 2021 Correction to Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML21173A1632021-08-0606 August 2021 Authorization and Safety Evaluation for Alternative Request No. RR-4-25 ML21201A1172021-08-0606 August 2021 Proposed Alternative Requests S1-I5-ISI-05 and S2-I5-ISI-06 to Eliminate Examination of Threads in Reactor Pressure Vessel Flange ML21112A1082021-06-30030 June 2021 Issuance of Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML20148M3592020-12-0808 December 2020 Issuance of Amendment Nos. 302 and 302 to Revise Technical Specifications Figure 3.1 1, Surry Units 1 and 2 Reactor Coolant System Heatup Limitations, and Figure 3.1-2, Surry Units 1 and 2 Reactor Coolant System ML20293A1602020-12-0808 December 2020 Issuance of Amendment Nos. 301 and 301 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20248H3782020-12-0202 December 2020 Alternative Requests RR 4-19 and RR-4-21 Related to the In-Service Testing Program (Epids L-2020-LLR-0077 and L-2020-LLR-0078) ML20321A2322020-11-20020 November 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20301A4522020-10-28028 October 2020 Non-Proprietary, Issuance of Amendment Nos. 300 and 300 to Revise Technical Specifications 6.2.C, Core Operating Limits Report ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI ML20085G9642020-05-19019 May 2020 Issuance of Amendments Nos. 298 and 298 to Revise Technical Specifications Table 3.7-1, Reactor Trip Instrument Operating Conditions, for an Addition of 24-Hour Completion Time for an Inoperable Rector Trip Breaker 2025-01-21
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September 15, 2023 Mr. Eric S. Carr Senior Vice President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2, AND VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 - REQUEST TO USE A PROVISION OF A PREVIOUS EDITION OF THE ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI, FOR NONDESTRUCTIVE EXAMINATIONS (EPID L-2023-LLR-0013)
Dear Mr. Carr:
By letter dated April 6, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23096A237), Dominion Energy (Dominion, the licensee) submitted an Alternative Request to the Nuclear Regulatory Commission (NRC) in accordance with paragraph 50.55a (z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) to use a previous edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code (ASME Code) at Surry Power Station (SPS), Units 1 and 2, and Virgil C.
Summer Nuclear Station (VCSNS), Unit 1, for its upcoming sixth and fifth 10-year inservice inspection (ISI) intervals, respectively. Specifically, Dominion requested approval to use the provisions in the 2013 Edition of the ASME Code,Section XI, for nondestructive examination (NDE) activities associated with examinations at the facilities in lieu of the 2019 Edition of the ASME Code,Section XI.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that Dominion has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(a)(1) and that the proposed alternative provides an acceptable level of quality and safety. Therefore, the NRC staff authorizes the use of the NDE-related provisions in the 2013 Edition of the ASME Code,Section XI, identified in the application, subject to the conditions and limitations outlined in 10 CFR 50.55a(b) for SPS, Units 1 and 2, sixth 10-year ISI interval and VCSNS fifth 10-year ISI interval. All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
If you have any questions, please contact Ed Miller at (301) 415-2481, or via email at Ed.Miller@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No(s). 50-280, 50-281, and 50-395
Enclosure:
Safety Evaluation cc: ListServ Michael T.
Markley Digitally signed by Michael T. Markley Date: 2023.09.15 12:47:07 -04'00'
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PROPOSED ALTERNATIVE TO USE CERTAIN PROVISIONS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESEEL CODE SECTION XI 2013 EDITION NONDESTRUCTIVE ENGINEERING REQUIREMENTS DOMINION ENERGY SURRY POWER STATION, UNITS 1 AND 2 VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 DOCKET NOS. 50-280, 50-281, AND 50-395
1.0 INTRODUCTION
By letter dated April 6, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23096A237), Dominion Energy (Dominion, the licensee) submitted an Alternative Request to the Nuclear Regulatory Commission (NRC) in accordance with paragraph 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) to use a previous edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code (ASME Code) at Surry Power Station (SPS), Units 1 and 2, and Virgil C.
Summer Nuclear Station (VCSNS), Unit 1, for their upcoming sixth and fifth 10-year inservice inspection (ISI) intervals, respectively. Specifically, Dominion requested approval to use the provisions in the 2013 Edition of the ASME Code,Section XI, for nondestructive examination (NDE) activities associated with examinations at the facilities in lieu of the 2019 Edition of the ASME Code,Section XI.
Dominion is requesting to use portions of the ASME Code,Section XI, 2013 Edition applicable to NDE in lieu of the 2019 Edition during SPS, Units 1 and 2, sixth 10-year ISI interval and VCSNS, Unit 1, fifth 10-year ISI intervals to provide commonality of the same ASME Code Edition and common corporate procedures that are implemented across the entire Dominion nuclear fleet.
2.0 REGULATORY EVALUATION
The ISI of ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Code and applicable edition and addenda as described by 10 CFR 50.55a(g), except where specific relief has been granted.
Pursuant to 10 CFR 50.55a(g)(4), states, in part, that ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions and addenda of the ASME BPV Code to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations state that inservice examination of components and system pressure tests conducted during the initial and subsequent 120-month (hereby referred to as 10-year) intervals must comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(a) of this section 18 months before the start of the 10-year interval, subject to any applicable conditions listed in 10 CFR 50.55a(b)(2). In accordance with 10 CFR 50.55a(a)(1)(ii)(C), the latest edition of the ASME Code is the 2019 Edition.
The NRC regulations in 10 CFR 50.55a(z), Alternatives to codes and standards requirements, states, in part, that alternatives to the requirements of 10 CFR 50.55a(b) through (h) of this section or portions thereof may be used when authorized by the NRC, if the licensee demonstrates that (1) the proposed alternative would provide an acceptable level of quality and safety; or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Dominion has submitted this request on the basis that a proposed alternative would provide an acceptable level of quality and safety.
3.0 TECHNICAL EVALUATION
3.1 Dominions Alternative Request 3.1.1 ASME Code Components Affected The applicable ASME code components affected is identified in Table 1.
Table 1: ASME Code Components Affected Code Class Class 1, 2, and 3 Reference ASME Section XI, 2013 Edition and ASME Section XI, 2019 Edition Components Class 1, 2, and 3 Examinations Examination Categories All, as related to NDE Methods and Requirements Items Numbers All, as related to NDE Methods and Requirements 3.1.2 Applicable Code Edition In its letter dated April 6, 2023, the licensee stated, in part, that the sixth 10-year interval of the SPS, Units 1 and 2, ISI Program and the fifth 10-year interval of the VCSNS, Unit 1, ISI Program will be based on the ASME Code,Section XI, 2019 Edition. The remaining Dominion Energy nuclear fleet plants (i.e., North Anna and Millstone Power Stations) are currently standardized on the 2013 Edition of the ASME Code for performance of NDE activities.
The SPS Units 1 sixth 10-year ISI interval begins on October 14, 2023, and ends on October 13, 2033. The SPS Unit 2 sixth 10-year ISI interval begins on May 10, 2024, and ends on May 9, 2034. The VCSNS fifth 10-year ISI interval begins on January 1 2024, and ends on December 31, 2033.
SPS and VCSNS are requesting approval to use the 2013 Edition of the ASME Code,Section XI for NDE activities associated with ISI for the SPS Units 1 and 2 sixth and VCSNS Unit 1 fifth 10-year ISI intervals.
3.1.3 Proposed Alternative and Basis for Use As stated in its letter dated April 6, 2023, the proposed alternative would allow SPS Units 1 and 2 and VCSNS Unit 1 to utilize provisions of the 2013 Edition instead of the 2019 Edition of ASME Code,Section XI for NDE activities related to performing ISI during the sixth 10-year ISI intervals for SPS Units 1 and 2 and the fifth 10-year ISI interval for VCSNS Unit 1.
Specifically, SPS and VCSNS are requesting the use of the provisions in the 2013 Edition of ASME Code,Section XI for NDE activities associated with inservice inspections. These NDE activities are driven by the ASME Code,Section XI, Subsection IWA, Articles IWA-1000 and IWA-2000, and Mandatory Appendices I, Ill, IV, VI, VII, and VIII.
The proposed alternative does not apply to the balance of the ISI Programs including the selection, planning, and scheduling of ISI examinations and tests as defined in IWB-, IWC-,
IWD-, and IWF-2500 or NRC approved ISI alternatives. Therefore, ISI examinations and tests will be selected, planned, and scheduled in accordance with the 2019 Edition of ASME Code,Section XI, which is the Code of Record for the SPS Units 1 and 2 sixth, and VCSNS Unit 1 fifth, 10-year ISI intervals. Further, this proposed alternative request will have no effect on any prior relief or alternative requests previously approved by the NRC.
In implementing this proposed alternative, SPS Units 1 and 2 and VCSNS Unit 1 will comply with all applicable NRC conditions and limitations related to the NDE requirements of the 2013 Edition of the ASME Code,Section XI specified in 10 CFR 50.55a(b)(2).
This alternative is requested for the sixth 10-year ISI interval for SPS Units 1 and 2, and for the fifth 10-year ISI interval for VCSNS Unit 1. The SPS Unit 1 sixth 10-year ISI interval begins on October 14, 2023, and ends on October 13, 2033. The SPS Unit 2 sixth 10-year ISI interval begins on May 10, 2024, and ends on May 9, 2034. The VCSNS fifth 10-year ISI interval begins on January 1, 2024, and ends on December 31, 2033.
3.2
NRC Staff Evaluation
The NRC staff evaluated Dominions alternative request, pursuant to 10 CFR 50.55a(z)(1). The NRC staffs evaluation focused on (1) whether there exists major difference between the requested provisions of licensees proposed edition (which is the 2013 Edition) and (2) the latest approved edition (which is the 2019 Edition) of the ASME Code,Section XI incorporated by reference in 50.55a(a), and whether applicable conditions in 50.55a will be met. The NRC staff finds that if these two criteria are met, the proposed alternative provides an acceptable level of quality and safety.
The licensee is requesting to use the provisions in the 2013 Edition of the ASME Code,Section XI, for NDE activities associated with ISI at SPS Units 1 and 2 and VCSNS Unit 1. The 2013 Edition of the ASME Code,Section XI is incorporated by reference into 10 CFR 50.55a(a)(1)(ii), except for Item Nos. B5.11 and B5.71 in Table IWB-2500-1 (B-F),
subparagraph IWB-3112(a)(3), and subparagraph IWC-3112(a)(3). The licensee has not requested to use any of the excluded provisions. Additionally, the licensee stated in the application that it will comply with all applicable conditions and limitations specified in 10 CFR 50.55a(b) for the applicable provisions of the 2013 Edition of ASME Code,Section XI.
Therefore, the first criterion has been satisfied.
The proposed alternative that Dominion submitted describes the major differences between the 2013 and 2019 edition of ASME Code,Section XI in Table 2 of the letter dated April 6, 2023.
The differences between the 2013 edition and 2019 edition of ASME Code,Section XI are minor and the changes in the 2019 Edition of ASME Code,Section XI are often relaxations in rigor, not increases in rigor. Therefore, the second criterion has been satisfied.
Based on the above, the NRC staff concludes that the criteria contained in 10 CFR 50.55a(z)(1) are satisfied and that the Dominions request to use provisions of the 2013 Edition of the ASME Code,Section XI for the NDE activities relating to the ISI examinations is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that Dominions proposed request to use the provisions in the 2013 Edition of the ASME Code,Section XI, for NDE activities associated with ISI examinations in lieu of the 2019 Edition, as described in their submittal, provides an acceptable level of quality and safety and is acceptable because the requirements in 10 CFR 50.55a(z)(1) are satisfied. Therefore, the NRC staff authorizes the use of the NDE-related provisions in the 2013 Edition of the ASME Code,Section XI, identified in the application, subject to the conditions and limitations in 10 CFR 50.55a(b) for the sixth 10-year ISI interval at SPS Units 1 and 2 and the fifth 10-year ISI interval at VCSNS Unit 1, as specified in the application.
All other ASME Code,Section XI, requirements for which the alternative was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor(s): Stephen Cumblidge, NRR Matt Burton, NRR Date: September 15, 2023
ML23230A001 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/LA NRR/DNRL/NPHP/BC NAME ZTurner GEMiller KGoldstein SCumblidge DATE 8/21/2023 8/29/2023 08/21/2023 8/31/2023 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley GEMiller DATE 9/15/2023 9/15/2023