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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
MONTHYEARIR 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 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000395/20240112024-06-26026 June 2024 – Comprehensive Engineering Team Inspection Report 05000395/2024011 ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2262024-03-26026 March 2024 License Amendment Request - Inverter Allowed Outage Time Extension Response to Request for Additional Information ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. ML24067A0232024-03-0707 March 2024 (Vcsns), Unit 1 - Readiness for 95001 Supplemental Inspection; EA-23-093 IR 05000395/20230062024-02-28028 February 2024 Annual Assessment Letter for Virgil C. Summer Nuclear Station - Report 05000395/2023006 IR 05000395/20244032024-02-27027 February 2024 Security Baseline Inspection Report 05000395/2024403 ML24057A1132024-02-22022 February 2024 Special Report 2024-001 Waste Gas System Inoperability ML24051A0112024-02-20020 February 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Proposed Project Location or May Be Affected by Proposed Project for V.C. Summer SLR ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24032A3062024-02-15015 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24040A1802024-02-12012 February 2024 Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000395/20244012024-02-0808 February 2024 Security Baseline Inspection Report 05000395/2024401 ML24038A0322024-02-0707 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 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping 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 2024-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML24180A0062024-08-0505 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 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 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 2024-08-05
[Table view] |
Text
February 9, 2017
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 REGARDING SERVICE WATER SYSTEM PIPING (CAC NO. MF9082)
Dear Mr. Lippard:
By letter dated January 13, 2017, South Carolina Electric & Gas Company (SCE&G, the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000, at Virgil C. Summer Nuclear Station, Unit 1. The licensee submitted Relief Request RR-4-11 to propose an alternative flaw evaluation to that of ASME Code Case N-513-3 "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1," ta disposition a pin hole leak in lieu of performing an ASME Code repair of the 8-inch, ASME Code Class 3 service water system piping. The licensee submitted the proposed alternative in accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2) on the basis that compliance with the specified ASME Code requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. On January 14, 2017, the Nuclear Regulatory Commission (NRC) verbally authorized the use of Relief Request RR-4-11 to disposition of the subject piping at Virgil C. Summer Nuclear Station, Unit 1, until the end of the April 2017 refueling outage (RF23), or exceeding the temporary acceptance criteria of Code Case N-513-3 and the relief request, whichever occurs first. The NRC staff determined that the proposed alternative is technically justified and provides a reasonable assurance of the structural integrity of the affected piping. This safety evaluation documents the technical basis for the NRC's verbal authorization. All other ASME Code requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
G. Lippard, Ill -2 -If you have any questions, please contact the Project Manager, Shawn Williams, at 301-415-1009 or Shawn.Williams@nrc.gov. Docket No. 50-395
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv
Sincerely,Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TEMPORARY ACCEPTANCE OF DEGRADATION IN SERVICE WATER PIPING 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 January 13, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17017A172), South Carolina Electric and Gas Company (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000, at Virgil C. Summer Nuclear Station (VCSNS), Unit 1. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee submitted Relief Request RR-4-11 to temporary accept a pin hole leak in lieu of performing an ASME Code repair of the degraded service water (SW) system piping based on ASME Code Case N-513-3 "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1," with a slight modification. On January 14, 2017 (ADAMS Accession No. ML 17017A217), the Nuclear Regulatory Commission (NRC) verbally authorized the use of Relief Request RR-4-11 to disposition of the subject piping at VCSNS, Unit 1, until the end of the April 2017 refueling outage (RF23), or exceeding the temporary acceptance criteria of Code Case N-513-3 and the relief request, whichever occurs first. The NRC staff determined that the proposed alternative is technically justified and provides a reasonable assurance of the structural integrity of the affected piping. This safety evaluation documents the technical basis for the NRC's verbal authorization. Enclosure
-2 -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. Pursuant to 10 CFR 50.55a(z) alternatives to requirements may be authorized by the NRC if the licensee demonstrates that: (1) the proposed alternatives 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. Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request the use of an alternative and the NRC to authorize the proposed alternative. 3.0 TECHNICAL EVALUATION 3.1 ASME Code Component Affected The affected component is the ASME Code Class 3, 8-inch weld neck flange of the SW system. The component is fabricated with carbon steel SA-105. 3.2 Applicable Code Edition and Addenda The ASME Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," 2007 Edition through 2008 Addenda. 3.3 Applicable Code Requirement The licensee is required to perform repair/replacement activities in accordance with Article IWA-4000 of the ASME Code,Section XI, 2007 Edition through 2008 Addenda. 3.4 Reason for Request On January 11, 2017, the licensee discovered a pin hole approximately 1.5 inches downstream of Diesel Generator Cooler 'A' SW Return Valve XVB03121A-SW. A mist was spraying onto an adjacent wall and running down the pipe at approximately 1 milliliter (ml) per minute. The licensee measured the affected pipe wall thickness using ultrasonic testing (UT). The licensee stated that an ASME Code repair is a hardship without a compensating increase in the level of quality and safety because a Code repair would require a plant shutdown to replace the pipe/valve flange. The flange is located between valve XVB03121A-SW and the service water pond. The flange cannot be isolated from other portions of the service water system piping. The licensee noted that the degraded condition is not in compliance with article IWA-4000 of the ASME Code,Section XI, 2007 Edition through 2008 Addenda. 3.4 Proposed Alternative and Basis for Use In lieu of an ASME Code repair, the licensee proposed to use modified ASME Code Case N-513-3 to temporary accept the pin hole leak as discussed below.
-3 -Flaw Characterization The licensee classified the degradation as a non-planar through wall flaw, and not a crack-type indication. The licensee noted that because of the wear mechanism, which has been identified as cavitation induced erosion, there is only a single identified flaw. The remaining area of the flange (other than the pin hole) has seen only nominal wall thinning based on the UT examination. Structural Integrity VCSNS, Unit 1, Technical Specification 4.0.5 states that the structural integrity of an ASME component is determined in accordance with either the original construction code or the ASME Code,Section XI, approved code cases or regulatory-approved methods of evaluation. The licensee noted that in the application of code case N-513-3, the flaw (the pin hole) meets all provisions of the code case except Section 1 (c) where the flaw falls beyond the distance of (Ro x t)A0.5 where Ro is the outside radius and 't' is the wall thickness of the pipe. The licensee performed a flaw evaluation to accept the flaw using guidance from ASME Code Case N-513-3 and ASME Code, Section Ill, 2007 Edition through 2008 Addenda. The licensee's evaluation results show the existing defect is structurally acceptable. The licensee noted that further degradation is acceptable as long as the average thickness of the remaining material outside the hole is greater than 0.02 inches within a diameter of 1.5 inch of the hole. Flow Margin The pin hole leak is located downstream of the 'A' Emergency Diesel Generator heat exchangers and downstream of the discharge valve XVB03121A-SW on the discharge line to the SW pond. A leak at this location does not affect the ability to provide cooling water to the emergency diesel generator heat exchangers. The current leakage from the pin hole is a fine mist which is less than 1 ml per minute. In its flow margin evaluation, the licensee conservatively assumed a leak rate of 11.5 gallons per minute (gpm) based on a 0.375 inch diameter hole at an internal pipe pressure of 20 pounds per square inch (psi). The SW pump is designed to supply 16,800 gpm of flow. A leak rate of 11.5 gpm from a 0.375 inch diameter hole would not have a significant effect on the performance of the pump. The licensee stated that a recent routine code check valve test on the SW 'A' Train measured the total system flow to be 12,953 gpm. The design minimum required post-accident flow for a train of SW is 12,237 gpm. The licensee noted that this check valve testing alignment is comparable to the post-accident SW system alignment. Therefore, there is a flow margin of approximately of 716 gpm (12,953 gpm -12, 237 gpm). The licensee stated that a postulated leakage of 11.5 gpm would not adversely affect SW system flow margin. The SW pond contains approximately 38.5E6 gallons of water and has the capability of being filled by a cross-tie valve from the circulating water system if water level drops below the alarm limit. The licensee noted that a postulated leak of 11.5 gpm would have a negligible affect the SW pond level. Spray Concerns The licensee stated that the current small stream of mist coming from the pin hole leak is directed toward the wall in the diesel building 427 foot elevation and is not currently adversely affecting any surrounding equipment. There is no active safety-related equipment that would be adversely impacted by the leakage. The system pressure is low at the defect location
-4 -(20 [pounds per square inch gauge] psig or less). Therefore, the only potential effect from the spray would be the open/close limit switches and the conduit/terminal box for the limit switches on valve XVB03121A-SW. The valve limit switches are only used for position indication because XVB03121 A-SW is a manual valve and no position change is required for the related function. If it is assumed that the existing defect opens to a 0.375 inch diameter hole, the orientation and location of the leak would lead to the resulting spray deflecting off the wall and pooling on the floor prior to affecting any equipment in the vicinity of the valve excluding the limit switches and associated conduit/terminal box for XVB03121A-SW. The closest equipment is the Diesel Generator Fuel Oil Transfer Pumps and these are approximately 15 feet away from the pin hole and on the other side of the valve. The spray would not have adequate velocity from the 0.375-inch hole at approximately 20 psi to adversely affect these pumps. Flooding In its flooding analysis, the licensee assumed a 30-minute operator action and no floor drain capability or sump pump operation. If it is assumed that the existing defect opens to a 0.375 inch diameter hole, the discharge would be approximately 11.5 gpm (at design upset pressure of 20 psig) and would increase the calculated flood level in the 400 foot elevation from 48.1 inches to 49.0 inches. The level in the 427 foot elevation is unaffected since the curb heights limit the water level in this elevation and any water cascading above these curbs will drain to the 400 foot level. The location of the pin hole leak is above the standing water level of the SW pond. Therefore, if the 'A' SW pump was secured, water from the SW pond would not back flow into the diesel building through the defect area. Under normal operating conditions, the diesel generator building sump pumps have a 40 gpm capacity each. There are two redundant 100 percent capacity sump pumps which can be used during normal plant operations. The diesel generator building sump pumps would have sufficient capacity to prevent building flooding from the postulated 11.5 gpm leak rate. The diesel generator building sump pumps are not available during a loss of offsite power. The water from the spray will collect at the floor near the pipe and drain to a nearby floor drain which goes to the Emergency Diesel Generator Building sump which has pumps to remove the excess water. Extent of Condition The licensee will implement an augmented examination in accordance with Section 5 of Code Case N-513-3. Compensatory Monitoring Plan The licensee will quantify the leakage from the pin hole leak at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the leak is repaired. The licensee will perform UT examinations of no more than 30 day intervals around the degraded area to characterize flaw growth. The licensee stated that the monitoring plan will remain in place until the SW system is removed from service and the degraded flange is repaired. 3.5 Duration of Proposed Alternative The licensee stated that it will complete a code compliant repair during the next refueling outage which is scheduled to start on April 8, 2017. Therefore, the duration of the proposed alternative
-5 -is approximately 4 months until repaired during the outage. The station is in its 4th 10-year interval effective from January 1, 2014, through and including December 31, 2023. 3.6 NRC Staff Evaluation The NRC staff evaluated the proposed alternative based on the provisions of ASME Code Case N-513-3, and the 2007 edition through 2008 addenda of the ASME Code, Sections 111 and XI as follows: Flaw Characterization The NRC staff finds that the licensee has used UT to measure the wall thickness of the affected area of the pipe. The licensee classified the degradation as a non-planar through wall flaw, not a crack. The NRC staff notes that the licensee has identified the degradation mechanism as cavitation induced erosion and that there is only a single identified flaw. The NRC staff finds that the licensee has satisfied the flaw characterization requirements of paragraphs 2(a) and 2(b) of Code Case N-513-3. Structural Integrity The nominal pipe size of the affected pipe segment is 8 inches. However, the pin hole is located on the flange portion of valve XVB03121A-SW which has a diameter that is larger than the nominal 8 inches. The licensee used an outer diameter of 9.6875 inches in its calculations. Based on the licensee's thickness measurement using UT, the unaffected wall thickness ranges from 0.317 inches to 0.348 inches. The lowest wall thickness of the affected area was measured to be about 0.085 inches. The NRC staff notes that the design pressure for the affected pipe and flange is 20 psi which is low. The licensee noted that further degradation is acceptable as long as the average thickness of the remaining material outside the hole is greater than 0.02 inches within a diameter of 1.5 inch of the hole. Based on independent calculations, the NRC staff determines that with a low pressure of 20 psi, the minimum required wall thickness would be less than 0.02 inches. As reported by the licensee, the minimum measured thickness in the vicinity of the leaking pin hole was about 0.085 inches. In addition, the licensee stated that it will quantify the leakage daily and perform wall thickness measurements every 30 days. The NRC staff finds that the likelihood of the degradation that will exceed the licensee proposed acceptance criteria without being detected is remote. The NRC staff finds that there is a sufficient margin in terms of flaw size and leak rate with respect to the acceptable limits. Therefore, the NRC staff finds that the structural integrity of the subject flange will be maintained until the next refueling outage based on the flaw evaluation and periodic monitoring plan. Flow Margin The NRC staff notes that the pin hole occurs on the section of the service water pipe that discharges to the SW pond. A leakage occurring in this pipe segment does not affect the safety function of the SW piping. However, a significant leak rate may affect the performance of the upstream SW pump. Based on the difference between the total measured test flow rate and the minimum required flow rate through SW piping, the licensee stated that a margin of 716 gpm exists. The NRC staff considers that a maximum allowable leak rate of 11.5 gpm would not challenge the flow margin of 716 gpm. The NRC staff finds that the SW has sufficient flow
-6 -margin to compensate for an allowable leak rate of 11.5 gpm and that a leak rate of 11.5 gpm will not affect the performance of the SW pump. Spray Concerns The NRC staff notes that the licensee has demonstrated that based on the orientation and location of a conservative 0.375 inch diameter leaking hole, no safety equipment and structure will be affected significantly. The NRC staff finds that the licensee has addressed the spray concern adequately. Flooding The NRC staff notes that the licensee evaluated the flooding based on a postulated 0.375-inch hole with a corresponding leak rate of 11.5 gpm. The NRC staff finds that the capacity of the diesel building sump pump (40 gpm) will be able to remove the leakage. During a loss of offsite power when the diesel building sump pump cannot operate, the leakage can be drained to the emergency diesel generator building sump which has pumps to remove leaking water. Therefore, NRC staff concludes that flooding is not a concern in the diesel generator pump building as a result of the leakage. Extent of Condition The NRC staff finds that the licensee has satisfied the extent of condition inspection because it will perform an augmented examination in accordance with Section 5 of Code Case N-513-3. Monitoring The NRC staff finds that the licensee has satisfied the monitoring requirements of Code Case N-513-3 because the licensee will quantify the leakage from the pin hole leak at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the leak is repaired. In addition, the licensee will perform UT examinations of no more than 30 day intervals around the degraded area to characterize flaw growth. On the basis of above evaluation, the NRC concludes that the licensee has demonstrated that the proposed alternative will provide reasonable assurance that the structural integrity of the subject SW piping and its intended safety function will be maintained. 4.0 CONCLUSION The NRC staff concludes that the proposed alternative provides a reasonable assurance of structural integrity of the subject SW piping. The NRC staff concludes that complying with IWA-4000 of the ASME Code,Section XI, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC authorizes the use of Relief Request RR-4-11 at VCSNS, Unit 1, until the end of the April 2017 refueling outage (RF23), or exceeding the temporary acceptance criteria of Code Case N-513-3 and the relief request, whichever occurs first.
-7 -All other requirements in ASME Code,Section XI, for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector. Principal Contributor: John Tsao Date: February 9, 2017