Letter Sequence Approval |
---|
EPID:L-2022-LLR-0033, Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) (Approved, Closed) |
|
MONTHYEARML22069B1172022-03-10010 March 2022 Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) Project stage: Request ML22082A0942022-03-25025 March 2022 Request for Withholding Information from Public Disclosure for Virgil C. Summer Nuclear Station, Unit No. 1, Request for Withholding, Application for Alternative Request Extension of Steam Generator Primary Inlet Nozzle Dissimilar Weld Insp Project stage: Withholding Request Acceptance ML22084A4052022-03-25025 March 2022 NRR E-mail Capture - Acceptance Review for Summer Dissimilar Metal Weld Inspection Interval (L-2022-LLR-0033) Project stage: Acceptance Review ML22224A0352022-08-12012 August 2022 Regulatory Audit Questions - Request for Alternative to ASME Operation and Maintenance Code Subsection ISTC-3630 Project stage: Other ML22300A2202022-10-27027 October 2022 (VCSNS) Unit 1, Alternative Request Rr-4-26 Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) RAI Project stage: Request ML22300A1842022-10-27027 October 2022 Revised Expected Submission Date for Supplement to Licensee Event Report 2022-002-00 Project stage: Request ML22341A1972022-12-15015 December 2022 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval Project stage: Approval 2022-03-10
[Table View] |
|
---|
Category:Letter
MONTHYEARML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 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 ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23137A1782023-05-22022 May 2023 Correction to Issuance of Amendment to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program 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 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 ML22242A1632022-08-31031 August 2022 Correction to Issuance of Amendment to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program 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 ML21112A1082021-06-30030 June 2021 Issuance of Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML19276D3772019-12-11011 December 2019 Issuance of Amendment Revise Company Name to Dominion Energy South Carolina, Inc. ML19080A1032019-04-30030 April 2019 Issuance of Amendment No. 215 Technical Specification 3.8.2, D.C. Sources - Operating ML19074A2222019-04-10010 April 2019 Issuance of Amendment No. 214 Removes the Expired One-Time Extension to Surveillance Requirement 4.3.3.6 and Removes the Index from Technical Specifications ML19023A4202019-03-0707 March 2019 Issuance of Amendment Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 ML19056A4062018-11-30030 November 2018 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Thermal Mixing Zone Evaluation 2018 Water Quality Monitoring Report ML18253A1152018-10-0505 October 2018 Issuance of Amendment No. 212 Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit ML18260A0272018-09-25025 September 2018 Issuance of Exigent Amendment One Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation ML18141A6682018-06-28028 June 2018 Issuance of Amendment No. 210, Revise Technical Specification 6.8.4.g for Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML18157A2122018-06-0707 June 2018 Correction to Amendment No. 199 to Correct an Administrative Error ML18108A1632018-04-20020 April 2018 Correction to Amendments Nos. 79 and 202, to Correct Typographical Errors ML18033A8442018-02-27027 February 2018 Correction to Amendment No. 170 to Correct a Typographical Error ML17206A4122017-10-0404 October 2017 Issuance of Amendment TSTF-411, Revision 1, Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P-A). ML17011A0502017-03-0909 March 2017 Issuance of Amendment to Revise Completion Date of Implementation Milestone 8 of the Cyber Security Plan ML16348A2002017-01-18018 January 2017 Issuance of Amendment to Revise Technical Specification 3.5.4 Limiting Condition for Operation Refueling Water Storage Tank ML16264A4112016-10-26026 October 2016 Issuance of Amendment to Revise Technical Specification 3/4.7.1.2, Emergency Feedwater System ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident ML16104A2952016-05-0606 May 2016 Issuance of Amendment to Adopt TSTF-523, Revision 2 RC-16-0043, License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System.2016-04-0707 April 2016 License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System. ML16063A0902016-03-0909 March 2016 Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2 RC-16-0035, (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B2016-03-0101 March 2016 (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B ML15208A0292015-10-15015 October 2015 Issuance of Amendment ML15170A0872015-08-18018 August 2015 Issuance of Amendment to Revise the Radiation Emergency Plan ML15063A3552015-04-13013 April 2015 Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6 ML14287A2892015-02-11011 February 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14122A3092014-05-29029 May 2014 Issuance of Amendment 198 Regarding the Cyber Security Plan Implementation Schedule Milestone 8 ML14030A3742014-03-11011 March 2014 Issuance of Amendment for Technical Specification Change Related to Control Room Emergency Filtration System ML14010A1822014-02-28028 February 2014 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-510 ML13354B6432014-02-0606 February 2014 Issuance of Amendment for the Technical Specification Change Related to Snubber Surveillance Requirements ML13326A2042014-02-0505 February 2014 Issuance of Amendment Extending Integrated Leak Rate Test Interval ML12292A0562012-12-21021 December 2012 Issuance of Amendment Regarding Deviation of Scope of the Cyber Security Plan Implementation and Facility Operating Condition 2.E ML12270A3012012-10-12012 October 2012 Issuance of Amendment ML12184A1352012-07-0909 July 2012 Issuance of Amendment ML12146A0172012-05-30030 May 2012 Issuance of Amendment on Beacon Core Monitoring and Operations Support System ML12121A0342012-05-0101 May 2012 Issuance of Amendment Extending Integrated Leak Rate Test ML11346A0062012-03-20020 March 2012 Issuance of Amendment Regarding Quality Assurance Program ML12047A1922012-03-0606 March 2012 Issuance of Amendment No. 187 Regarding Surveillance Frequency of Solids State Protection Westinghouse Type AR Relays 18 Months ML11326A2502012-02-22022 February 2012 Issuance of Amendment Regarding Reactor Coolant System Leakage Detection Systems ML11201A3122011-08-24024 August 2011 Issuance of Amendment 184 Regarding Cyber Security Plan ML1021600202010-10-0404 October 2010 Issuance of Amendment Regarding Alternative Source Term Implementation ML1001103772010-03-22022 March 2010 Issuance of Amendment Regarding: Use of Optimized Zirlo Fuel Rod Cladding 2023-05-22
[Table view] Category:Safety Evaluation
MONTHYEARML23250A3112023-09-20020 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 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 ML23062A7292023-03-31031 March 2023 Deferral of Pressurizer and Steam Generator Weld Examinations 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 ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program 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 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 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 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) ML19361A0702020-01-24024 January 2020 Relief Request Regarding Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography (RR-4-20) ML19276D3772019-12-11011 December 2019 Issuance of Amendment Revise Company Name to Dominion Energy South Carolina, Inc. ML19242E0272019-09-0606 September 2019 Relief Request (RR-4-22) for Use of ASME Code Case N-513-4 ML19140A4732019-06-0404 June 2019 Relief Request (RR-4-23) to Utilize Code Case N-513-4 ML19080A1032019-04-30030 April 2019 Issuance of Amendment No. 215 Technical Specification 3.8.2, D.C. Sources - Operating ML19074A2222019-04-10010 April 2019 Issuance of Amendment No. 214 Removes the Expired One-Time Extension to Surveillance Requirement 4.3.3.6 and Removes the Index from Technical Specifications ML19023A4202019-03-0707 March 2019 Issuance of Amendment Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 ML19035A2992019-02-26026 February 2019 Relief Request (RR-4-18) for Use of NRC Generic Letter 90-05 ML19030B8272019-02-13013 February 2019 Relief Request (RR-4-17) for Use of ASME Code Case N-513-3 ML19003A1882019-01-18018 January 2019 Relief Request (RR-4-16) for Use of ASME Code Case N-513-4 and NRC Generic Letter 90-05 ML18345A0602018-12-17017 December 2018 Relief Request Regarding Use of a Performance Based Testing Frequency for Pressure Isolation Valves (RR-4-14) ML18296A1112018-11-0808 November 2018 Relief Request (RR-4-15) for Use of ASME Code Case N-513-4 ML18253A1152018-10-0505 October 2018 Issuance of Amendment No. 212 Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit ML18260A0272018-09-25025 September 2018 Issuance of Exigent Amendment One Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation ML18255A2562018-09-24024 September 2018 Correction to the Safety Evaluation and the Orders Approving Indirect Transfer of Licenses ML18129A0762018-08-30030 August 2018 Transmittal Letter and Safety Evaluation Related to the Orders Approving Indirect Transfer of Licenses for Units 1, 2, 3 and the Independent Spent Fuel Storage Installation ML18186A5882018-07-19019 July 2018 Relief Request (RR-4-13) for Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds. ML18141A6682018-06-28028 June 2018 Issuance of Amendment No. 210, Revise Technical Specification 6.8.4.g for Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML17206A4122017-10-0404 October 2017 Issuance of Amendment TSTF-411, Revision 1, Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P-A). ML17089A6172017-08-0101 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17011A0502017-03-0909 March 2017 Issuance of Amendment to Revise Completion Date of Implementation Milestone 8 of the Cyber Security Plan ML17031A0152017-02-0909 February 2017 Relief from the Requirements of the ASME Code Regarding Service Water System Piping ML16348A2002017-01-18018 January 2017 Issuance of Amendment to Revise Technical Specification 3.5.4 Limiting Condition for Operation Refueling Water Storage Tank ML16264A4112016-10-26026 October 2016 Issuance of Amendment to Revise Technical Specification 3/4.7.1.2, Emergency Feedwater System ML16161A0452016-07-0101 July 2016 Relief from the Requirements of the ASME Code ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident ML16104A2952016-05-0606 May 2016 Issuance of Amendment to Adopt TSTF-523, Revision 2 ML16124A8972016-05-0606 May 2016 Relief from the Requirements of the ASME Code ML16063A0902016-03-0909 March 2016 Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2 ML15208A0292015-10-15015 October 2015 Issuance of Amendment ML15222A5422015-09-0101 September 2015 Alternative Request Regarding Root Mean Square Depth Sizing Requirements ML15170A0872015-08-18018 August 2015 Issuance of Amendment to Revise the Radiation Emergency Plan ML15176A3152015-08-12012 August 2015 Alternative Request Regarding Snubbers ML15063A3552015-04-13013 April 2015 Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6 2023-09-20
[Table view] |
Text
December 15, 2022 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - RE: EXTENSION OF STEAM GENERATOR PRIMARY INLET NOZZLE DISSIMILAR METAL WELD INSPECTION INTERVAL (EPID L-2022-LLR-0033)
Dear Mr. Stoddard:
By letter dated March 10, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML22069B117 (Request) and ML22069B118 (Proprietary Attachment), as supplemented by letter dated October 27, 2022 (ML22300A220), Dominion Energy South Carolina (Dominion, the licensee), submitted a request for the Virgil C. Summer Nuclear Station, Unit No. 1 (Summer), to the U.S. Nuclear Regulatory Commission (NRC or Commission) for a proposed alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code), Section XI.
Specifically, Dominion requested a one-time extension of the Summer steam generator primary inlet nozzle dissimilar metal weld inspection interval from five years to nominally nine years for the volumetric examination. In its supplement dated October 27, 2022, the licensee modified the request for two possible durations for the alternative. The first was through the fall refueling outage (RFO) in 2024 and the second was through the spring RFO in 2026. The NRC staffs review considered the shorter duration through the fall RFO in 2024.
The NRC staff has reviewed the alternative request and concludes, as set forth in the enclosed safety evaluation, that Dominion has adequately addressed all the regulatory requirements set forth in 10 CRR 50.55a(z)(1). 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.
D. Stoddard If you have any questions, please contact the Project Manager, Ed Miller at 301-415-2481 or via e-mail at Ed.Miller@nrc.gov.
Sincerely, Digitally signed by Michael Michael T. T. Markley Date: 2022.12.15 07:57:06 Markley -05'00' Michael T. Markley, Chief Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-395
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION EXTENSION OF STEAM GENERATOR PRIMARY INLET NOZZLE DISSIMILAR METAL WELD INSPECTION INTERVAL DOMINION ENERGY SOUTH CAROLINA VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated March 10, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML22069B117 (Request) and ML22069B118 (Proprietary Attachment), as supplemented by letter dated October 27, 2022 (ML22300A220), Dominion Energy South Carolina (Dominion, the licensee), submitted a request for the Virgil C. Summer Nuclear Station, Unit No. 1 (Summer), to the U.S. Nuclear Regulatory Commission (NRC or Commission) for a proposed alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code), Section XI.
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 will meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code, Section XI.
Paragraph 10 CFR 50.55a(z) states, in part, that alternatives to the requirements of 10 CFR 50.55a(b)-(h) may be used, when authorized by the Director, Office of Nuclear Reactor Regulation, if (1) the proposed alternatives 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.
The licensee has submitted this request on the basis that a proposed alternative would provide an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1).
Enclosure
3.0 TECHNICAL EVALUATION
3.1 Licensee's Proposed Alternative
Applicable Code Edition and Addenda
The applicable Code Edition and Addenda is the ASME Code, Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, 2007 Edition through 2008 Addenda.
American Society of Mechanical Engineers (ASME) Code Components Affected The request is applicable to the following components and associated dissimilar metal welds (DMW):
1-4100A-31 (DM) - A SG Inlet Nozzle to Safe End DMW 1-4200A-28 (DM) - B SG Inlet Nozzle to Safe End DMW 1-4300A-29 (DM) - C SG Inlet Nozzle to Safe End DMW ASME Code Requirement for Which Alternative Is Requested Paragraph 10 CFR 50.55a(g)(6)(ii)(F)(1) requires licensees to implement the requirements of ASME BPV Code Case N770-5, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (16) of the section.
The proposed alternative covers examinations required by American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-770-5, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities, Section XI, Division 1 (ASME Code Case N-770-5).
Specifically, the examinations are for welds that fall under ASME Code Case N-770-5, Inspection Item A-2: Unmitigated butt weld at Hot Leg operating temperature < 625 °F (329 C).
Components inspected under Item A-2 require a visual examination each refueling outage and volumetric examination every five years.
Proposed Alternative and Basis for Use The licensee is proposing a one-time extension of the steam generator (SG) primary inlet nozzle dissimilar metal (DM) weld inspection interval at Virgil C. Summer Nuclear Station (Summer),
Unit 1 from five years to nominally six years for the volumetric examination only. No changes are requested to the visual examination requirements of the SG inlet nozzle DM welds. The SG inlet nozzle DM welds were volumetrically examined in the fall of 2018. The next scheduled volumetric examination for these welds is in the spring of 2023. The licensee requested to defer the volumetric examination.
Duration of Proposed Alternative Dominion requested a one-time extension of the Summer steam generator primary inlet nozzle DMW inspection interval from five years to nominally nine years for the volumetric examination.
In its supplement dated October 27, 2022, the licensee modified the request for two possible durations for the alternative. The first was through the fall refueling outage (RFO) in 2024 and the second was through the spring RFO in 2026. The NRCs review considered the shorter duration through the fall RFO in 2024.
3.2 NRC Staff Evaluation The licensee requested an extension of the inspection interval for the subject N-770-5, Inspection Item A-2 welds from five years to six years. The basis used to demonstrate the acceptability of extending the examination interval for Code Case N-770-5, Inspection Item A-2 components is contained in the site-specific weld crack growth analysis described in Enclosure 3 of the letter dated March 10, 2022, and the crack growth information provided in its supplement letter dated October 27, 2022.
The weld crack growth analyses is intended to demonstrate that the welds possess adequate thickness to protect against failure due to primary water stress corrosion cracking (PWSCC). In the weld crack growth analyses, an inside surface flaw that is 1.7 mm (0.065 in), or fifty percent of the depth of the inlay is postulated in the PWSCC-resistant Alloy 52 inlay. Then, the analysis calculated the amount of time for the flaw to reach the maximum allowable end-of-evaluation period flaw size. This maximum allowable end-of-evaluation period flaw size would be the largest flaw size that could exist in the welds and still be acceptable according to ASME Code, Section XI. Crack growth was calculated based on the PWSCC growth mechanism through both the Alloy 52 inlay and the Alloy 82 DM welds.
Using the same inputs and methodology discussed in the original request, the licensees supplement letter dated October 27, 2022, provided analyses at two lower Factors of Improvement (15 and 23), and proposed two possible durations for the alternative. The first was through the fall refueling outage (RFO) in 2024 and second was through the spring RFO in 2026. The Nuclear Regulatory Commission (NRC) is currently working with the PWSCC Crack Growth Rate Expert Panel, which is evaluating the crack growth PWSCC data for Alloys 52 and 152, including several data sets not included in the letter dated March 10, 2022. The NRC staff has determined that until the work of the Expert Panel is completed that longer-term alternatives are challenging to support and that the Fall of 2024 is the more appropriate duration for proposed alternative RR-4-26. If this work is completed in the near future, the NRC would consider authorizing longer duration alternative requests.
The results of the analysis justify a longer examination interval for the welds than the five years currently allowed for Code Case N-770-2, Inspection Item A-2 welds. Based on the results for the SG inlet nozzle DM welds hot leg, an examination interval of up to six years is acceptable.
The plant-specific PWSCC growth results, in the attached Westinghouse letter and technical report, supports the request for the Summer Unit 1 SG inlet nozzle DM welds to be examined after a duration of six years from the previous refueling outage inspections in fall of 2018. This would allow Summer Unit 1 to perform the inspection during the fall 2024 refueling outage.
In the event that a crack is present and grows faster than predicted by the crack growth analyses, the licensee has programs in place to detect leakage though the welds during outages and during operation. The licensee performs bare metal visual examinations of the
subject welds every refueling outage. The licensee has a boric acid corrosion control program that monitors for signs of boric acid deposits. Additionally, the licensee uses containment radiation monitors and monitors containment sump levels plant operation to detect substantial reactor coolant system leakage and/or increases in radiation levels within containment that would occur in the unlikely event of leakage through the welds.
Based on the above, the NRC staff finds that the licensees analysis demonstrates that it is unlikely that an unacceptable crack would be present during the extended interval. Additionally, if such a crack were to develop, the licensee has monitoring programs and administrative controls in place that would likely detect the crack and allow remedial action to be taken.
Therefore, the NRC concludes that re-examination interval provides an acceptable level of quality and safety through the RFO in fall 2024.
4.0 CONCLUSION
All other ASME Code, Section XI requirements for which relief has not been specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: S. Cumblidge, NRR Date: December 15, 2022
ML22341A197 *Via SE Input OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DNRL/NPHP/BC NRR/DORL/LPL2-1/BC NAME GEMiller KGoldstein MMitchell* MMarkley DATE 12/12/2022 12/08/2022 12/6/2022 12/15/2022 OFFICE NRR/DORL/LPL2-1/PM NAME GEMiller DATE 12/15/2022