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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] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station
- Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 -ALTERNATIVE REQUEST DURING THE FOURTH TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MF5457)
Dear Mr. Gatlin:
By letter dated December 18, 2014, South Carolina Electric & Gas Company (SCE&G, the licensee), submitted an alternative request to the U.S. Nuclear Regulatory Commission (NRC).
The licensee proposed to apply the methodology previously covered under Generic Letter 89-04, Position 9 for quarterly Group A inservice testing of Charging/Safety Injection pumps.
The application was submitted pursuant to Section 50.55a (z)(1) of Title 10 of the Code of Federal Regulations ( 10 CFR), which requires the applicant to demonstrate that the proposed alternative would provide an acceptable level of quality and safety.
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 50.55a (z)(1 ), and therefore authorizes the proposed alternative.
T. Gatlin If you have any questions, please contact the Project Manager, Shawn Williams, at 301.-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Sincerely, Robert J. Pascarelli, 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 ALTERNATIVE REQUEST RR-4-06 FOURTH 10-YEAR INSERVICE INSPECTION PROGRAM INTERVAL SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated December 18, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14356A560), South Carolina Electric & Gas Company (SCE&G),
the licensee, submitted an alternative request RR-4-06 to the U.S. Nuclear Regulatory Commission (NRC). The licensee requested an alternative test plan in lieu of certain inservice testing (1ST) requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the 1ST program at Virgil C. Summer Nuclear Station (VCSNS) Unit 1 during the fourth 10-year 1ST program interval, which began on January 1, 2014, and is currently scheduled to conclude on December 31, 2023.
The application was submitted pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (1 0 CFR), which requires the applicant to demonstrate that the proposed alternative would provide an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
10 CFR 50.55a(f), "lnservice Testing Requirements," requires, in part, that 1ST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs (z)( 1) or (z)(2).
In proposing alternatives, a licensee must demonstrate that the proposed alternatives provide an acceptable level of quality and safety (1 0 CFR 50.55a(z)(1 )) or compliance would result in hardship or unusual difficulty Without a compensating increase in the level of quality and safety (10 CFR 50.55a(z)(2)).
Enclosure
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1.1 Licensee's Alternative Request RR-4-06 ASME OM Code Requirements:
ISTB-3000, "General Testing Requirements," states, in part, the parameters to be measured during preservice and inservice testing are specified in Table ISTB-3000-1.
Table ISTB-3000-1, "lnservice Test Parameters," specifies, in part, that Flow Rate (Q) is required to be measured during Group A pump preservice and inservice testing.
ISTB-351 O(a), "Accuracy," states, in part, instrument accuracy shall be within the limits of Taple ISTB-3510-1. If a parameter is determined by analytical methods instead of measurement, then the determination shall meet the parameter accuracy requirement of Table .
ISTB-3510-1.
ISTB-3550, "Flow Rate," states, When measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall include the method used to reduce the data. Internal recirculated flow is not required to be measured. External recirculated flow is not required to be measured if it is not practical to isolate, has a fixed resistance, and has been evaluated by the Owner to not have substantial effect on the results of the test.
ISTB-5100, "Centrifugal Pumps (Except Vertical Line Shaft Centrifugal Pumps)," Part A, "Duration of Tests," (1) states, For the Group A test and the comprehensive test, after pump conditions are as stable as the system permits, each pump shall be run at least 2 minutes. At the end of this time at least one measurement or determination of each of the quantities required by Table ISTB-3000-1 shall be made and recorded.
ISTB-5121(c), "Group A Test Procedure," states, Where itis not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values.
ISTB-5121 (e), "Group A Test Procedure," states in part, All deviations from the reference values shall be compared with the ranges of Table ISTB-5121-1 and corrective action taken as specified in ISTB-6200.
Alternative testing is requested for the following pumps:
Table 1 Pump ID Function Group Class XPP0043A Charging/Safety Injection Pump A 2 XPP0043B Charging/Safety Injection Pump A 2 XPP0043C Charging/Safety Injection Pump A 2 The *licensee states in part:
Reason for Request
VCSNS's Charging/Safety Injection (SI) System was constructed without installed flow measurement instrumentation in the Charging/SI System minimum-flow recirculation lines.
During the previous two test intervals Charging/SI Pump inservice testing was conducted in accordance with Generic Letter (GL) 89-04 Position 9.
Efforts were undertaken to measure flow through the recirculation lines using ultrasonic flow meters prior to the new interval. Strap-on ultrasonic flow meters have been used during the first 12 months of the new interval to measure recirculation flow during Charging/SI Pump quarterly
- Group A testing. The required instrument repeatability established in ASME OM Code Table ISTB-351 0-1 could not be achieved. During field use, flow rate variations of up to 6 percent and higher from average were noted. Inaccuracies associated with clamp-on ultrasonic flow measurement devices were the subject of NRC Information Notice (IN) 95-08, "Inaccurate Data Obtained with Clamp-on Ultrasonic Flow Measurement Instruments."
Relief from the requirement to measure recirculation line flow during Charging/SI Pump Group A testing is requested based on the lack of consistency in data measurement using the ultrasonic meters and lack of installed instrumentation.
Proposed Alternative VCSNS has historically performed a quarterly surveillance test without measuring the recirculation line flow rate as provided for in GL 89-04, Position 9. VCSNS has attempted to measure flow with ultrasonic flow meters but has not been successful. Through this relief request, VCSNS proposes to use the previous method as identified in GL 89-04 as an alternative method for meeting the surveillance requirement, therefore, maintaining an acceptable level of quality and safety. Performing inservice testing using a non-instrumented recirculation line was previously found acceptable by the NRC in GL 89-04, Position 9, "Pump Testing using Minimum-flow Return Line With or Without Flow Measuring Devices," when an instrumented flow path was available during refueling for measuring flow at a substantial flow rate.
Pump flow is measured during a comprehensive test each refueling outage with the minimum-flow line isolated. Pump performance is then compared to Design Basis Accident analysis requirements.
The Group A pump quarterly test of the Charging/SI Pumps will be performed in accordance with GL 89-04, Position 9, measuring pump differential pressure and vibration. The Charging/SI Pump orifices are large differential pressure orifices, with backpressure having minimal effect on orifice performance.
- Using the provisions of this request as an alternative to the requirements of ISTB-3000, Table ISTB-3000-1, ISTB-51 OO(a), and ISTB-5121 provides a reasonable alternative to the Code requirements based on the determination that the proposed alternative will provide adequate indication of pump performance, permit detection of component degradation, and continue to provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(z)(1 ),
VCSNS requests approval of this alternative to the specific ISTB requirements identified in this request.
SCE&G will implement the alternative requirements during the fourth 10-year In service Testing interval at VCSNS, Unit 1, which began January 1, 2014, and ends December 31, 2023.
3.1.2 NRC Staff Evaluation ASME OM Code 2004 Edition through 2006 Addenda Section ISTB-5221 (c), "Group A Test Procedure," states: Where system resistance cannot be varied, flow rate and pressure shall be determined and compared to their respective reference values. ASME OM Code Section ISTB-3300(e)(2), "Reference Values," states: Reference values shall be established within
+/-20% of pump design for the Group A and Group B tests, if practicable. If not practicable, the reference point flow shall pe established at the highest practical flow rate. ASME OM Code Section ISTB-351 O(a), "Accuracy," states in part: Instrument accuracy shall be within the limits of Table ISTB-351 0-1. If a parameter is determined by analytical methods instead of measurement, then the determination shall meet the parameter accuracy requirement of Table ISTB-3510-1 (e.g., flow rate determination shall be accurate to within +/-2% of actual). ASME OM Code Section ISTB-3550, "Flow Rate," states in part: When measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit.
Charging/Safety Injection pumps XPP0043A, XPP0043B, and XPP0043C are defined as Group A pumps per the ASME OM Code. During normal plant operation, at least one charging pump is continuously in service. The second pump is a non-running pump on the inactive loop and the third, if available, is designated as a spare and its breaker(s) are racked out. The non-running pumps may be tested during power operation via the minimum flow bypass lines.
During the first 12 months of the new 1ST interval, the licensee has attempted to meet the Code requirement of measuring flow set at a prescribed reference value as directed by Section ISTB-5121, "Group A Test Procedure" by using external strap-on ultrasonic flow instrumentation on the minimum flow bypass lines for the standby pumps. However, due to the design of the minimum flow bypass lines and the limitations of the ultrasonic flow instrumentation, difficulty in achieving the accuracy requirements of ISTB-351 O(a) were encountered. The licensee has proposed an alternative to quarterly test using the minimLJm flow path lines without installed flow rate instrumentation. Measurements will include differential pressure across the pump and vibration in accordance with ASME OM Code-2004 through 2006 Addenda Section ISTB-5121.
The NRC staff has reviewed the licensee's proposed alternative and has determined that the testing is consistent with the guidance in NUREG-1482, Revision 2, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices," and GL 89-04, "Guidance On Developing Acceptable lnservice Testing Programs," Position 9. The proposed alternative provides an acceptable level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff finds that the proposed alternative described in alternative request RR-4-06 provides an acceptable level of quality and safety for pumps listed in Table 1.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, the NRC staff authorizes the proposed alternative in request RR-4-06 for the fourth 1ST interval at VCSNS which began on January 1, 2014, and is currently scheduled to end on December 31, 2023.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests for relief remain applicable.
Principle Contributor: Michael Farna11, NRR Dated: January 9, 2015
T. Gatlin If you have any questions, please contact the Project Manager, Shawn Williams, at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Sincerely,
/RAJ Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
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