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Category:Code Relief or Alternative
MONTHYEARML24026A2802024-01-25025 January 2024 Acceptance Review for Virgil C. Summer Relief Requests RR-5-V1, RR-5-V2, and RR-5-V3 (EPIDs L-2023-LLR-0067, L-2023-LLR-0068, and L-2023-LLR-0069) (Email) ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23062A7292023-03-31031 March 2023 Deferral of Pressurizer and Steam Generator Weld Examinations 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) 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 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 ML19091A0582019-01-10010 January 2019 Draft Application Related to April 4, 2019, Pre-Application Public Meeting for Two Proposed Relief Request 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 RC-18-0070, (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ...2018-10-0808 October 2018 (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ... RC-18-0118, (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange2018-09-14014 September 2018 (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange RC-18-0105, (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water ..2018-08-14014 August 2018 (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water .. 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. ML17031A0152017-02-0909 February 2017 Relief from the Requirements of the ASME Code Regarding Service Water System Piping ML16161A0452016-07-0101 July 2016 Relief from the Requirements of the ASME Code ML16124A8972016-05-0606 May 2016 Relief from the Requirements of the ASME Code ML15176A3152015-08-12012 August 2015 Alternative Request Regarding Snubbers ML15007A1612015-01-0909 January 2015 Alternative Request During the Fourth Ten-Year Inservice Inspection Interval ML14079A6142014-03-24024 March 2014 Acceptance Review Concerning Alternative Request RR-4-05 Alternative Weld Repair for Reactor Vessel Upper Head Penetrations R-4-04 ML13301A7672013-11-0505 November 2013 Relief Request (RR-4-01, RR-4-02, RR-4-03) for Third and Fourth Ten- Year Inservice Inspection Interval (TAC Nos. MF1900, 1901, 1902) ML13177A0782013-07-0808 July 2013 Acceptance Review Concerning Relief from Limited Pressurizer Surge Nozzle-to-Vessel Examination (TAC No. MF1848)(RC-13-0068) ML13101A3332013-04-19019 April 2013 Alternative RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration (TAC No. ME9851) (RC-12-0165) RC-12-0179, Relief Request RR-III-09 Request for Information Fatigue Crack Growth and Transients2012-11-16016 November 2012 Relief Request RR-III-09 Request for Information Fatigue Crack Growth and Transients RC-12-0165, Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration2012-10-30030 October 2012 Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration ML12289A0502012-10-17017 October 2012 Alternative RR-III-08 for Third 10-Year Inservice Inspection Interval ML0630705402006-11-21021 November 2006 Relief Requests RR-111-03 and RR-111-04, Relief from Certain Examination Qualification Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code., RC-06-0117, Relief, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)2006-06-20020 June 2006 Relief, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04) ML0601004482006-01-20020 January 2006 Relief, Second 10-year Inservice Inspection, Requests for Relief RR-II-9, RR-II-10, & RR-II-12 ML0523006162005-09-0606 September 2005 Relief Request, RI-ISI Program ML0512901982005-05-10010 May 2005 Relief, Relief Request No. RR-III-01 Snubber Visual Examination and Functional Testing RC-04-0148, Request to Use Alternatives to ASME Code Requirements in Plant Third Inservice Inspection Interval (RR-111-01, RR-111-02)2004-09-0808 September 2004 Request to Use Alternatives to ASME Code Requirements in Plant Third Inservice Inspection Interval (RR-111-01, RR-111-02) ML0410503842004-04-0707 April 2004 Request to Use Alternative to ASME Code Requirements in VCSNS Third Inservice Inspection Interval ML0404203862004-02-11011 February 2004 2/11/04, Virgil C. Summer Nuclear Station, Bwn, Relief Request RR-11-16 Regarding Reduced Ultrasonic Testing, TAC No. MC0108 RC-03-0234, Submittal of Information Requested by NRC for Evaluation of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI RR-II-18 (0-C-03-0262)2003-11-13013 November 2003 Submittal of Information Requested by NRC for Evaluation of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI RR-II-18 (0-C-03-0262) RC-03-0223, Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-15, RR-II-18 (0-C-03-0262)2003-10-23023 October 2003 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-15, RR-II-18 (0-C-03-0262) ML0330101602003-10-23023 October 2003 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-11,RR-II-12(0-C-02-3202) RC-03-0196, Resubmittal of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI (C-03-0262), RR-II-15, RR-II-16, RR-II-17, RR-II-192003-09-16016 September 2003 Resubmittal of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI (C-03-0262), RR-II-15, RR-II-16, RR-II-17, RR-II-19 RC-03-0191, Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI2003-09-11011 September 2003 Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI RC-03-0142, Request for Use Alternatives to ASME Boiler & Pressure Vessel Code, Section XI, RR-II-15, RR-11-15, RR-II-17, RR-II-18, RR-II-19, RR-II-20 and RR-II-212003-07-11011 July 2003 Request for Use Alternatives to ASME Boiler & Pressure Vessel Code, Section XI, RR-II-15, RR-11-15, RR-II-17, RR-II-18, RR-II-19, RR-II-20 and RR-II-21 ML0317402382003-06-13013 June 2003 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-13 (0-C-03-0883) 2024-01-25
[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: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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 6, 2016 Mr. George A. Lippard, Ill Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88, Mail Code 800 Jenkinsville, SC 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - RELIEF FROM THE REQUIREMENTS OF THE ASME CODE (CAC NO. MF7085)
Dear Mr. Lippard:
By letter dated November 10, 2015, as supplemented by letter dated March 18, 2016, South Carolina Electric & Gas Company (SCE&G, the licensee) submitted Relief Request RR-111-12, to the U.S. Nuclear Regulatory Commission (NRC) for the third 10-year inservice inspection (ISi) interval of the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this approval is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. The four remaining ASME Code Class 1 piping welds submitted in the November 10, 2015, application will be addressed in separate correspondence under CAC No. MF7098.
The application was submitted pursuant to Title 10 of the Code of Federal Regulations 50.55a(g)(5)(iii). The licensee requested relief and to use alternative requirements (if necessary), for ISi on the basis that the B&PV Code requirement is impractical.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that SCE&G has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(6)(i) and, therefore, authorizes the proposed alternative for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2.
G. Lippard, Ill If you have any questions, please contact the Project Manager, Shawn Williams, at 301-415-1009 or Shawn.Williams@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RR-111-12 REGARDING ASME CODE CLASS 2 VESSEL WELDS CGE-2-1110-1 B/1 AND CGE-2-1110-1 B/2 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated November 10, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15316A556), as supplemented by letter dated March 18, 2016 (ADAMS Accession No. ML16083A214), South Carolina Electric & Gas Company (the licensee) submitted Relief Request RR-111-12 to the U.S. Nuclear Regulatory Commission (NRC) for the third 10-year inservice inspection (ISi) interval of the Virgil C. Summer Nuclear Station, Unit 1 (Summer). In Relief Request RR-111-12, the licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (8&PV Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this review is for the two ASME Code Class 2 vessel welds, CGE-2-1110-18/1 and CGE-2-1110-18/2, in the residual heat removal (RHR) heat exchanger shell identified in the licensee's submittal. These two welds are ASME Code,Section XI, Examination Category C-A welds, Item No. C1 .20.
The application was submitted pursuant to Title 10 of the Code of Federal Regulations 50.55a(g)(5)(iii). The licensee requested relief and to use alternative requirements (if necessary), for ISi on the basis that the 8&PV Code requirement is impractical.
2.0 REGULATORY EVALUATION
The ISi of ASME Code Class 1, 2, and 3 components is performed in accordance with Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components, of the 8&PV Code and applicable edition and addenda, as required by 10 CFR 50.55a(g). When conformance to these requirements is determined to be impractical, relief may be granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). Additionally, pursuant to 10 CFR 50.55a(g)(6)(i), the NRC may impose such alternative requirements, as it determines are authorized by law, that will not endanger life or property or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Enclosure
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals complies 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), 12 months prior to the start of the 120-month interval, subject to the conditions in 10 CFR 50.55a(b)(2). The code of record for Summer for the third 10-year ISi interval is the 2000 Addenda to the 1998 Edition of the ASME Code,Section XI.
The regulation in 10 CFR 50.55a(g)(5)(iii) states, in part, that determinations of impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the ASME Code requirements during the ISi interval for which the request is being submitted. Requests for relief made in accordance with this section must be submitted to the NRC no later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought. The licensee submitted Relief Request RR-111-12 on August 10, 2015, for the third 10-year ISi interval of Summer, which ended on December 31, 2013. As indicated in the submittal, in accordance with the ASME Code,Section XI, paragraph IWA-2430(c)(1 ), the licensee extended the third ISi 10-year interval of Summer to end on December 31, 2014.
3.0 TECHNICAL EVALUATION
The information provided by the licensee in support of Relief Request RR-111-12 regarding welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2 has been evaluated, and the bases for disposition are documented below.
ASME Code Component Identification ASME Code Class: ASME Code,Section XI, Class 2 Examination Category: C-A Item Number: C1 .20, Pressure Retaining Welds in Pressure Vessels Component: RHR Heat Exchanger Weld Numbers: CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2 ASME Code Requirements The applicable examination requirement for welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2 is essentially 100 percent volumetric examination of the weld length, as specified in Table IWC-2500-1, "Examination Categories," of the ASME Code,Section XI, Examination Category C-A, Item No. C1 .20. When 100 percent of the required volume cannot be examined due to interferences, obstructions, or geometrical configuration, ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds," allows reduction of the examination volume to 90 percent of the required volume. ASME Code Case N-460 has been approved for use by the NRC in Regulatory Guide 1.147, Revision 17, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1."
Licensee's Relief Request The licensee achieved less than 90 percent coverage of the required examination volume due to the geometric configuration and obstructions inherent in the design of the RHR heat exchanger.
The licensee achieved 43.9 percent coverage of the required examination volume for weld CGE-2-1110-1 B/1 due to the flange on the upstream side of the weld and the two saddle plates attached to the RHR heat exchanger shell. For weld CGE-2-1110-1 B/2, the licensee achieved 87.8 percent coverage of the required examination volume due to the two saddle plates attached to the RHR heat exchanger shell. These limitations, inherent in the design of the RHR heat exchanger in the region of the subject welds, make the ASME Code-required examination coverage impractical. Plant modifications or replacement of components to allow for complete coverage would be needed to meet the ASME Code requirements.
Licensee's Proposed Alternative (as stated by the licensee)
Examination of welds/components was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, 1998 Edition through 2000 Addenda. Summer has examined the subject welds to the maximum extent possible utilizing approved examination techniques and equipment. Based on the limited coverage achieved by the examinations performed, it is the position of the station that the limited examinations provide a reasonable assurance of quality and safety.
NRC Staff Evaluation
The licensee achieved 43.9 percent coverage of the required examination volume for weld CGE-2-1110-1 B/1 due to the flange on the upstream side of the weld and the two saddle plates attached to the RHR heat exchanger shell. Weld CGE-2-1110-1 B/2 achieved 87.8 percent coverage of the required examination volume due to the two saddle plates attached to the RHR heat exchanger shell. As such, obtaining the ASME Code-required examination volumes for these two welds would require significant modification of the RHR heat exchanger shell, which imposes a burden upon the licensee.
The licensee stated that the examination was performed with ultrasonic examination procedure SCANA-UT-98-13. By NRC letter dated February 18, 2016 (ADAMS Accession No. ML16042A471 ), the staff requested the licensee in Request for Additional Information (RAI)
No. 1 to discuss the ASME Code Section XI, Appendix I, requirement on which procedure SCANA-UT-98-13 is based. By letter dated March 18, 2016, the licensee stated that the requirement of Subarticle 1-2200 of Appendix I to Section XI of the ASME Code is applicable to procedure SCANA-UT-98-13. Subarticle 1-2200 of Appendix I to Section XI of the ASME Code states that ultrasonic examination of vessels not greater than 2 inches in thickness shall be performed in accordance with Appendix Ill to Section XI of the ASME Code, with the applicable supplements in Table 1-2000-1 "Required Supplements," of Appendix I to Section XI of the ASME Code. The staff verified that the thickness of the RHR heat exchanger shell applicable to welds CGE-21110-1 B/1 and CGE-2-1110-1 B/2 is less than 2 inches. Based on the above, the NRC staff concludes the licensee's response to RAI No. 1 is acceptable.
Welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2 were examined to the maximum extent possible, using 45-degree shear wave search units, scanning both parallel and perpendicular to the weld. Weld CGE-2-1110-1 B/1 is limited to scanning only one side of the weld due to the flange configuration on the other side of the weld. Weld CGE-2-1110-1 B/2 was scanned on both sides of the weld. The examined volumes of both welds included the weld and base material near the inside surface of the weld joint, which are regions of high stress, and where one would expect degradation to be manifested, should it occur.
During the ultrasonic examinations of welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, the licensee detected inside surface geometries that were previously recorded and verified at similar locations and similar search unit amplitudes. The staff confirmed that these inside surface geometries were recorded in the previous (second) 10-year ISi interval submittal (SCE&G letter dated September 16, 2003, ADAMS Accession No. ML032690223).
By NRC letter dated February 18, 2016, in RAI No. 2, the staff requested the licensee to discuss any plant-specific operating experience regarding potential degradation in welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2. By letter dated March 18, 2016, in its response to the staff's RAI No. 2, the licensee stated that there is no plant-specific operating experience regarding potential degradation in welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2. Therefore, the NRC staff concludes that the response to RAI No. 2 is acceptable. Based on the examination coverage obtained for the subject weld, if significant service-induced degradation were occurring, the NRC staff concludes there is reasonable assurance that evidence of degradation would be detected by the examination coverage achieved.
Based on the above, the NRC staff determined that obtaining the ASME Code-required examination volume is impractical because it would impose a burden upon the licensee. The staff also determined that the volumetric ultrasonic examination performed to the maximum extent possible provides reasonable assurance of the structural integrity of welds CGE-2-1110-1B/1 and CGE-2-1110-1B/2 in Relief Request RR-111-12.
4.0 CONCLUSION
As set forth above, the staff has determined that with respect to welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest, given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Furthermore, the staff concludes that the licensee's examinations were performed to the maximum extent possible and that they provide reasonable assurance of the structural integrity of the subject RHR heat exchanger shell welds. Accordingly, the staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(6)(i). Therefore, the staff grants relief from the ASME Code examination requirements for welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2 in the RHR heat exchanger included in Relief Request RR-111-12 for the Summer third 10-year ISi interval.
All other requirements of Section XI of the ASME Code for which relief was not specifically requested and approved in the subject relief request remain applicable, including third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: David Dijamco Date: May 6, 2016
ML16124A897 *Internal Package ML16124A008 OFFICE DORL/LPLI 1-1 /PM DORL/LPLI 1-1 /LA DE/EVI B/BC* DORL/LPLll-1/BC NAME SWilliams LRonewicz JMcHale MMarkley DATE 5/4/16 5/4/16 5/2/16 5/6/16